transuranic waste hazardous: Topics by WorldWideScience.org

Sample records for transuranic waste hazardous

Certification plan transuranic waste: Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

1992-06-01

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
Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A

International Nuclear Information System (INIS)

WINTERHALDER, J.A.

1999-01-01

This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial
Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL2A

Energy Technology Data Exchange (ETDEWEB)

WINTERHALDER, J.A.

1999-09-29

This hazardous waste determination report (Report) describes the process and information used on the Hanford Site to determine that waste stream number NPFPDLZA, consisting of 30 containers of contact-handled transuranic debris waste, is not hazardous waste regulated by the Resource Conservation and Recovery Act (RCRA) or the New Mexico Hazardous Waste Act. For a waste to be hazardous under these statutes, the waste either must be specifically listed as a hazardous waste, or exhibit one or more of the characteristics of a hazardous waste, Le., ignitability, corrosivity, reactivity, or toxicity. Waste stream NPFPDLZA was generated, packaged, and placed into storage between 1993 and 1997. Extensive knowledge of the waste generating process, facility operational history, and administrative controls and operating procedures in effect at the time of generation, supported the initial nonhazardous waste determination. Because of the extent and reliability of information pertaining to this waste type, and the total volume of waste in the debris matrix parameter category, the Hanford Site is focusing initial efforts on this and similar waste streams for the first shipment to the Waste Isolation Pilot Plant (WIPP). RCRA regulations authorize hazardous waste determinations to be made either by using approved sampling and analysis methods or by applying knowledge of the waste in light of the materials or the process(es) used. This latter approach typically is referred to as process knowledge. The Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) for WIPP refers to acceptable knowledge in essentially the same terms; acceptable knowledge as used throughout this Report is synonymous with the term process knowledge. The 30 containers addressed in this Report were characterized by the following methods: Acceptable knowledge; Nondestructive examination using real-time radiography; Visual examination; and Headspace gas sampling and analysis. The initial
Transuranic contaminated waste functional definition and implementation

International Nuclear Information System (INIS)

Kniazewycz, B.G.

1980-03-01

The purpose of this report is to examine the problem(s) of TRU waste classification and to document the development of an easy-to-apply standard(s) to determine whether or not this waste package should be emplaced in a geologic repository for final disposition. Transuranic wastes are especially significant because they have long half-lives and some are rather radiotoxic. Transuranic radionuclides are primarily produced by single or multiple neutron capture by U-238 in fuel elements during the operation of a nuclear reactor. Reprocessing of spent fuel elements attempts to remove plutonium, but since the separation is not complete, the resulting high-activity liquids still contain some plutonium as well as other transuranics. Likewise, transuranic contamination of low-activity wastes also occurs when the transuranic materials are handled or processed, which is primarily at federal facilities involved in R and D and nuclear weapons production. Transuranics are persistent in the environment and, as a general rule, are strongly retained by soils. They are not easily transported through most food chains, although some reconcentration does take place in the aquatic food chain. They pose no special biological hazard to humans upon ingestion because they are weakly absorbed from the gastrointestional tract. A greater hazard results from inhalation since they behave like normal dust and fractionate accordingly
Alternative disposal options for transuranic waste

International Nuclear Information System (INIS)

Loomis, G.G.

1994-01-01

Three alternative concepts are proposed for the final disposal of stored and retrieved buried transuranic waste. These proposed options answer criticisms of the existing U.S. Department of Energy strategy of directly disposing of stored transuranic waste in deep, geological salt formations at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The first option involves enhanced stabilization of stored waste by thermal treatment followed by convoy transportation and internment in the existing WIPP facility. This concept could also be extended to retrieved buried waste with proper permitting. The second option involves in-state, in situ internment using an encapsulating lens around the waste. This concept applies only to previously buried transuranic waste. The third option involves sending stored and retrieved waste to the Nevada Test Site and configuring the waste around a thermonuclear device from the U.S. or Russian arsenal in a specially designed underground chamber. The thermonuclear explosion would transmute plutonium and disassociate hazardous materials while entombing the waste in a national sacrifice area
Transuranic waste characterization sampling and analysis plan

International Nuclear Information System (INIS)

1994-01-01

Los Alamos National Laboratory (the Laboratory) is located approximately 25 miles northwest of Santa Fe, New Mexico, situated on the Pajarito Plateau. Technical Area 54 (TA-54), one of the Laboratory's many technical areas, is a radioactive and hazardous waste management and disposal area located within the Laboratory's boundaries. The purpose of this transuranic waste characterization, sampling, and analysis plan (CSAP) is to provide a methodology for identifying, characterizing, and sampling approximately 25,000 containers of transuranic waste stored at Pads 1, 2, and 4, Dome 48, and the Fiberglass Reinforced Plywood Box Dome at TA-54, Area G, of the Laboratory. Transuranic waste currently stored at Area G was generated primarily from research and development activities, processing and recovery operations, and decontamination and decommissioning projects. This document was created to facilitate compliance with several regulatory requirements and program drivers that are relevant to waste management at the Laboratory, including concerns of the New Mexico Environment Department
Defense transuranic waste program strategy document

International Nuclear Information System (INIS)

1982-07-01

This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment
Hazardous and radioactive waste incineration studies

International Nuclear Information System (INIS)

Vavruska, J.S.; Stretz, L.A.; Borduin, L.C.

1981-01-01

Development and demonstration of a transuranic (TRU) waste volume-reduction process is described. A production-scale controlled air incinerator using commercially available equipment and technology has been modified for solid radioactive waste service. This unit successfully demonstrated the volume reduction of transuranic (TRU) waste with an average TRU content of about 20 nCi/g. The same incinerator and offgas treatment system is being modified further to evaluate the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood
Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In
Evaluation of a self-guided transport vehicle for remote transportation of transuranic and other hazardous waste

Energy Technology Data Exchange (ETDEWEB)

Rice, P.M.; Moody, S.J.; Peterson, R. [and others

1997-04-01

Between 1952 and 1970, over two million cubic ft of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory`s Radioactive Waste Management Complex. Commingled with this two million cubic ft of waste is up to 10 million cubic ft of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate a technology for transporting exhumed transuranic wastes at the Idaho National Engineering and Environmental Laboratory (INEEL) and at other hazardous or radioactive waste sites through the U.S. Department of Energy complex. The full-scale demonstration, conducted at the INEEL Robotics Center in the summer of 1995, evaluated equipment performance and techniques for remote transport of exhumed buried waste. The technology consisted of a Self-Guided Transport Vehicle designed to remotely convey retrieved waste from the retrieval digface and transport it to a receiving/processing area with minimal human intervention. Data were gathered and analyzed to evaluate performance parameters such as precision and accuracy of navigation and transportation rates.
Evaluation of a self-guided transport vehicle for remote transportation of transuranic and other hazardous waste

International Nuclear Information System (INIS)

Rice, P.M.; Moody, S.J.; Peterson, R.

1997-04-01

Between 1952 and 1970, over two million cubic ft of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex. Commingled with this two million cubic ft of waste is up to 10 million cubic ft of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate a technology for transporting exhumed transuranic wastes at the Idaho National Engineering and Environmental Laboratory (INEEL) and at other hazardous or radioactive waste sites through the U.S. Department of Energy complex. The full-scale demonstration, conducted at the INEEL Robotics Center in the summer of 1995, evaluated equipment performance and techniques for remote transport of exhumed buried waste. The technology consisted of a Self-Guided Transport Vehicle designed to remotely convey retrieved waste from the retrieval digface and transport it to a receiving/processing area with minimal human intervention. Data were gathered and analyzed to evaluate performance parameters such as precision and accuracy of navigation and transportation rates
Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the US Department of Energy waste management programmatic environmental impact statement

International Nuclear Information System (INIS)

Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.; Chang, Y.S.

1996-12-01

This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II) and presents the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)
Hazardous gas production by alpha particles in solid organic transuranic waste matrices. 1998 annual progress report

International Nuclear Information System (INIS)

LaVerne, J.A.

1998-01-01

'This project uses fundamental radiation chemical techniques to elucidate the basic processes occurring in the heavy-ion radiolysis of solid hydrocarbon matrices such as polymers and organic resins that are associated with many of the transuranic waste deposits or the transportation of these radionuclides. The environmental management of mixed waste containing transuranic radionuclides is difficult because these nuclides are alpha particle emitters and the energy deposited by the alpha particles causes chemical transformations in the matrices accompanying the waste. Most radiolysis programs focus on conventional radiation such as gamma rays, but the chemical changes induced by alpha particles and other heavy ions are typically very different and product yields can vary by more than an order of magnitude. The objective of this research is to measure the production of gases, especially molecular hydrogen, produced in the proton, helium ion, and carbon ion radiolysis of selected solid organic matrices in order to obtain fundamental mechanistic information on the radiolytic decomposition of these materials. This knowledge can also be used to directly give reasonable estimates of explosive or flammability hazards in the storage or transport of transuranic wastes in order to enhance the safety of DOE sites. This report summarizes the work after eight months of a three-year project on determining the production of hazardous gases in transuranic waste. The first stage of the project was to design and build an assembly to irradiate solid organic matrices using accelerated ion beams. It is necessary to measure absolute radiolytic yields, and simulate some of the conditions found in the field. A window assembly was constructed allowing the beam to pass consecutively through a collimator, a vacuum exit window and into the solid sample. The beam is stopped in the sample and the entire end of the assembly is a Faraday cup. Integration of the collected current, in conjunction
ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

International Nuclear Information System (INIS)

O'Leary, Gerald A.

2007-01-01

Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquaeters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approch include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safetly remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact
Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the U.S. Department of Energy waste management programmatic environmental impact statement

International Nuclear Information System (INIS)

Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.

1995-04-01

This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II), as well as providing the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)
Defense Transuranic Waste Program Strategy Document

International Nuclear Information System (INIS)

1984-01-01

The Defense Transuranic Waste Program (DTWP) Strategy Document presents the general strategy for managing transuranic (TRU) waste materials generated during defense and research activities regulated by the US Department of Energy. The Strategy Document includes discussion of objectives and activities relating to the entire Defense Transuranic Waste Program. However, the primary focus is on the specific management responsibilities of the Transuranic Waste Lead Organization (TLO). The document also includes an updated summary of progress on TLO-managed activities over the past year
Hanford site implementation plan for buried, transuranic-contaminated waste

International Nuclear Information System (INIS)

1987-05-01

The GAO review of DOE's Defense Waste Management Plan (DWMP) identified deficiencies and provided recommendations. This report responds to the GAO recommendations with regard to the Hanford Site. Since the issuance of the DWMP, an extensive planning base has been developed for all high-level and transuranic waste at the Hanford Site. Thirty-three buried sites have been identified as possibly containing waste that can be classified as transuranic waste. Inventory reports and process flowsheets were used to provide an estimate of the radionuclide and hazardous chemical content of these sites and approximately 370 additional sites that can be classified as low-level waste. A program undertaken to characterize select sites suspected of having TRU waste to refine the inventory estimates. Further development and evaluation are ongoing to determine the appropriate remedial actions, with the objectives of balancing long-term risks with costs and complying with regulations. 18 refs., 7 figs., 6 tabs
Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility
Long-term management plan INEL transuranic waste

International Nuclear Information System (INIS)

McKinney, J.D.

1978-12-01

The Idaho National Engineering Laboratory stores large quantities of transuranic-contaminated waste at its Radioactive Waste Management Complex. This report presents a 10-year plan for management of this transuranic waste and includes descriptions of projects involving nuclear waste storage, retrieval, processing, systems analysis, and environmental science. Detailed project schedules and work breakdown charts are provided to give the reader a clear view of transuranic waste management objectives
Transuranic elements and nuclear wastes

International Nuclear Information System (INIS)

Bowen, V.T.

1974-01-01

The contamination of oceans and marine life by transuranic elements (elements of atomic number greater than 92) is the main concern of this paper. Wastes of three different types, low-level, intermediate-level, and high-level, are considered. Fallout of Pu and other transuranics is discussed as it affects marine biogeochemistry and geochemistry. Different paths of absorption or uptake under various conditions of release are pointed out in some detail. The transfer of radioactivity to mammals from marine sources is considered in some detail. Waste disposal practices at Windscale are reviewed. It is concluded that the problems associated with transuranic wastes in oceans and marine life are very complex. Monitoring of waste release and uptake is concluded to not be enough. Each situation of release of transuranics to the environment should be treated as an experiment and milked for all the information that it can reveal. The tremendous expenditure of money and manpower necessary for such an undertaking is stressed

Overview of DOE's Transuranic Waste Program

International Nuclear Information System (INIS)

McFadden, M.H.; Detamore, J.A.

1987-01-01

The US Department of Energy has assigned to Albuquerque Operations the Defense Transuranic Waste Program responsibility for long-range planning and management of defense transuranic (TRU) waste. The Transuranic Waste Lead Organization (TLO) has divided the Program into seven elements which support it's primary goal of ending interim storage and achieving permanent disposal. These are: waste generation site activities, storage site activities, burial site activities, technology development, transportation, institutional activities, and permanent disposal. This paper will briefly discuss these seven elements and how they are integrated to provide for successful achievement of the primary goal
Transuranic waste management program and facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted
Transuranic Waste Management Program and Facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-02-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted
Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

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

1994-03-01

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 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
Overview of DOE's transuranic waste program

International Nuclear Information System (INIS)

McFadden, M.H.; Detamore, J.A.

1988-01-01

The United States Department of Energy (DOE) has assigned to Albuquerque Operations the Defense Transuranic Waste Program (DTWP) responsibility for long-range planning and management for defense transuranic (TRU) waste. The Transuranic Waste Lead Organization (TLO) has divided the Program into seven elements that support its primary goal of ending interim storage and achieving permanent disposal. These elements include waste generation site activities, storage site activities, burial site activities, technology development, transportation, institutional activities and permanent disposal. This paper briefly discusses these seven elements and how they are integrated to provide for successful achievement of the primary goal
Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Swanson, J.L.; Ross, W.A.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes
Transuranic solid waste management programs. Progress report, July--December 1975

International Nuclear Information System (INIS)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites
Transuranic solid waste management programs. Progress report, July--December 1975

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites.
Containment of transuranic contamination at the early waste retrieval project

International Nuclear Information System (INIS)

Harness, J.L.; McKinney, J.D.

1977-01-01

On July 26, 1976, while retrieving buried transuranic waste under the Early Waste Retrieval Program, a corroded 55-gallon 17H drum was retrieved. When uprighted, several liters of liquid escaped from the drum. This liquid was contaminated with transuranics, principally Pu-239, Am-241, and some Pu-238. As a result of the spread of this contamination in the Operating Area Confinement, six working days were required to decontaminate the area. At no time did the contamination escape the interior of the Operating Area Confinement building, and no contamination to personnel resulted from this occurrence, nor was a hazard presented to the general public. The facility was designed and constructed to contain the transuranic contamination resulting from such an occurrence. Proper prior planning and personnel training prevented the contamination occurrence from becoming a major event. This report details the occurrence, the recovery, and the information obtained from this event
Treatment strategies for transuranic wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Ross, W.A.; Swanson, J.L.; Allen, R.P.; Yasutake, K.M.

1986-01-01

This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these wastes (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes
Hanford site transuranic waste sampling plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed
Transuranic waste: long-term planning

International Nuclear Information System (INIS)

Young, K.C.

1985-07-01

Societal concerns for the safe handling and disposal of toxic waste are behind many of the regulations and the control measures in effect today. Transuranic waste, a specific category of toxic (radioactive) waste, serves as a good example of how regulations and controls impact changes in waste processing - and vice versa. As problems would arise with waste processing, changes would be instituted. These changes improved techniques for handling and disposal of transuranic waste, reduced the risk of breached containment, and were usually linked with regulatory changes. Today, however, we face a greater public awareness of and concern for toxic waste control; thus, we must anticipate potential problems and work on resolving them before they can become real problems. System safety analyses are valuable aids in long-term planning for operations involving transuranic as well as other toxic materials. Examples of specific system safety analytical methods demonstrate how problems can be anticipated and resolution initiated in a timely manner having minimal impacts upon allocation of resource and operational goals. 7 refs., 1 fig
Using an information system to meet Hazardous Waste Management needs

International Nuclear Information System (INIS)

Stewart, J.J. Jr.; Howe, R.E.; Townsend, S.L.; Maloy, D.T.; Kochhar, R.K.

1995-02-01

Lawrence Livermore National Laboratory (LLNL) is a large quantity RCRA hazardous waste generator. LLNL also generates low level and transuranic radioactive waste that is managed in accordance with the Department of Energy (DOE) orders. The mixed low level and mixed transuranic waste generated must be managed to comply with both RCRA regulations and DOE orders. LLNL's hazardous and radioactive waste generation is comprised of 900 generators who contribute to nearly two hundred waste streams. LLNL has a permitted EPA treatment and storage (TSD) facility for handling RCRA hazardous waste that is operated by LLNL's Hazardous Waste Management (HWM) division. In HWM we have developed an information system, the Total Waste Management System (TWMS), to replace an inadequate ''cradle to grave'' tracking of all the waste types described above. The goals of this system are to facilitate the safe handling and storage of these hazardous wastes, provide compliance with the regulations and serve as an informational tool to help HWM manage and dispose of these wastes in a cost effective manner
Plans for Managing Hanford Remote Handled Transuranic (TRU) Waste

International Nuclear Information System (INIS)

MCKENNEY, D.E.

2001-01-01

The current Hanford Site baseline and life-cycle waste forecast predicts that approximately 1,000 cubic meters of remote-handled transuranic (RH-TRU) waste will be generated by waste management and environmental restoration activities at Hanford. These 1,000 cubic meters, comprised of both transuranic and mixed transuranic (TRUM) waste, represent a significant portion of the total estimated inventory of RH-TRU to be disposed of at the Waste Isolation Pilot Plant (WIPP). A systems engineering approach is being followed to develop a disposition plan for each RH-TRU/TRUM waste stream at Hanford. A number of significant decision-making efforts are underway to develop and finalize these disposition plans, including: development and approval of a RH-TRU/TRUM Waste Project Management Plan, revision of the Hanford Waste Management Strategic Plan, the Hanford Site Options Study (''Vision 2012''), the Canyon Disposal Initiative Record-of-Decision, and the Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (SW-EIS). Disposition plans may include variations of several options, including (1) sending most RH-TRU/TRUM wastes to WIPP, (2) deferrals of waste disposal decisions in the interest of both efficiency and integration with other planned decision dates and (3) disposition of some materials in place consistent with Department of Energy Orders and the regulations in the interest of safety, risk minimization, and cost. Although finalization of disposition paths must await completion of the aforementioned decision documents, significant activities in support of RH-TRU/TRUM waste disposition are proceeding, including Hanford participation in development of the RH TRU WIPP waste acceptance criteria, preparation of T Plant for interim storage of spent nuclear fuel sludge, sharing of technology information and development activities in cooperation with the Mixed Waste Focus Area, RH-TRU technology demonstrations and deployments, and
Impact of dynamic certification requirements on the Nuclear Materials Technology Division's transuranic waste management program

International Nuclear Information System (INIS)

Balkey, J.J.; Montoya, A.J.; Wieneke, Ronald E.

2002-01-01

The issuance of the Waste Isolation Pilot Plant's (WIPP) Hazardous Waste Facility Permit in August of 2000, specifically the attachment I3 Waste Analysis Plan (WAP),had a profound impact upon transuranic (TRU) waste certification at Los Alamos National Laboratory's (LANL) Plutonium Facility. Program certification was lost until Laboratory internal program documents could be amended to meet the new WAP requirements, waste management personnel could be retrained to incorporate the changes into waste operations and the entire program successfully pass subsequent Carlsbad Field Ofice (CBFO) audit. This action resulted in the suspension of transuranic waste shipments from LANL to WIPP. In addition the changes unnecessarily increased the complexity of TRU waste program activities in waste handling.
Process to separate transuranic elements from nuclear waste

Science.gov (United States)

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

1989-03-21

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.
Process to separate transuranic elements from nuclear waste

International Nuclear Information System (INIS)

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

1989-01-01

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
Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams

International Nuclear Information System (INIS)

Montoya, A.J.; Gruetzmacher, K.; Foxx, C.; Rogers, P.S.Z.

1998-01-01

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site-specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the transuranic waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility's mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC
Transuranic waste transportation issues in the United States

International Nuclear Information System (INIS)

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

1988-01-01

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

International Nuclear Information System (INIS)

Bennett, W.S.; Crisler, L.R.

1981-01-01

To ensure that all technology necessary for long term management of transuranic (TRU) wastes is available, the Department of Energy has established the Transuranic Waste Management Program. A principal focus of the program is development of waste forms that can accommodate the very diverse TRU waste inventory and meet geologic isolation criteria. The TRU Program is following two approaches. First, decontamination processes are being developed to allow removal of sufficient surface contamination to permit management of some of the waste as low level waste. The other approach is to develop processes which will allow immobilization by encapsulation of the solids or incorporate head end processes which will make the solids compatible with more typical waste form processes. The assessment of available data indicates that dewatered concretes, synthetic basalts, and borosilicate glass waste forms appear to be viable candidates for immobilization of large fractions of the TRU waste inventory in a geologic repository

Proceedings of emerging technologies for hazardous waste management

International Nuclear Information System (INIS)

Tedder, D.W.

1992-01-01

This paper contains the proceedings of emergin technologies for hazardous waste management. Topics covered include: advanced transuranic waste managements; remediation of soil/water systems contaminated with nonaqueous pollutants; advances in molten salt oxidation; air treatment and protection; advanced waste minimization strategies; removal of hazardous materials from soils or groundwater; bioremediation of soils and sediment; innovation, monitoring, and asbestos; high-level liquid waste chemistry in the Hanford tanks; biological contributions to soil and groundwater remediation; soil treatment technologies; pollution prevention; incineration and vitrification; current technology; systematic design approaches to hazardous waste management; waste management and environmental restoration at Savannah River; soil washing and flushing for remediation of hazardous wastes
Implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bullock, M.G.; Rodriguez, R.R.

1987-05-01

This document presents the current implementation plans for buried transuranic waste and stored special-case waste at the Idaho National Engineering Laboratory. Information contained in this report was also included in several Department of Energy (DOE) planning documents for the Defense Transuranic Waste Program. This information can be found in the following DOE documents: Comprehensive Implementation Plan for the DOE Defense Buried TRU Waste Program; Defense Waste Management Plan for Buried Transuranic-Contaminated Waste, Transuranic-Contaminated Waste, Transuranic-Contaminated Soil, and Difficult-to-Certify Transuranic Waste; and Defense Special-Case Transuranic Waste Implementation Plan. 11 refs
RETRIEVING SUSPECT TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS PROGRESS PLANS AND CHALLENGES

International Nuclear Information System (INIS)

FRENCH, M.S.

2006-01-01

This paper describes the scope and status of the program for retrieval of suspect transuranic (TRU) waste stored in the Hanford Site low-level burial grounds. Beginning in 1970 and continuing until the late 1980's, waste suspected of containing significant quantities of transuranic isotopes was placed in ''retrievable'' storage in designated modules in the Hanford burial grounds, with the intent that the waste would be retrieved when a national repository for disposal of such waste became operational. Approximately 15,000 cubic meters of waste, suspected of being TRU, was placed in storage modules in four burial grounds. With the availability of the national repository (the Waste Isolation Pilot Plant), retrieval of the suspect TRU waste is now underway. Retrieval efforts, to date, have been conducted in storage modules that contain waste, which is in general, contact-handled, relatively new (1980's and later), is stacked in neat, engineered configurations, and has a relatively good record of waste characteristics. Even with these optimum conditions, retrieval personnel have had to deal with a large number of structurally degraded containers, radioactive contamination issues, and industrial hazards (including organic vapors). Future retrieval efforts in older, less engineered modules are expected to present additional hazards and difficult challenges
Transportation packagings for high-level wastes and unprocessed transuranic wastes

International Nuclear Information System (INIS)

Wilmot, E.L.; Romesberg, L.E.

1982-01-01

Packagings used for nuclear waste transport are varied in size, shape, and weight because they must accommodate a wide variety of waste forms and types. However, this paper will discuss the common characteristics among the packagings in order to provide a broad understanding of packaging designs. The paper then discusses, in some detail, a design that has been under development recently at Sandia National Laboratories (SNL) for handling unprocessed, contact-handled transuranic (CHTRU) wastes as well as a cask design for defense high-level wastes (HLW). As presently conceived, the design of the transuranic package transporter (TRUPACT) calls for inner and outer boxes that are separated by a rigid polyurethane foam. The inner box has a steel frame with stainless steel surfaces; the outer box is similarly constructed except that carbon steel is used for the outside surfaces. The access to each box is through hinged doors that are sealed after loading. To meet another waste management need, a cask is being developed to transport defense HLW. The cask, which is at the preliminary design stage, is being developed by General Atomic under the direction of the TTC. The cask design relies heavily on state-of-the-art spent-fuel cask designs though it can be much simpler due to the characteristics of the HLW. A primary purpose of this paper is to show that CHTRU waste and defense HLW currently are and will be transported in packagings designed to meet the hazards of transportation that are present in general commerce
Transuranic contaminated waste form characterization and data base

International Nuclear Information System (INIS)

McArthur, W.C.; Kniazewycz, B.G.

1980-07-01

This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report
Transuranic contaminated waste form characterization and data base

Energy Technology Data Exchange (ETDEWEB)

McArthur, W.C.; Kniazewycz, B.G.

1980-07-01

This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report.
In situ vitrification of transuranic wastes: An updated systems evaluation and applications assessment

Energy Technology Data Exchange (ETDEWEB)

Buelt, J.L.; Timmerman, C.L.; Oma, K.H.; FitzPatrick, V.F.; Carter, J.G.

1987-03-01

In situ vitrification (ISV) is a process whereby joule heating immobilizes contaminated soil in place into a durable glass and crystalline waste form. Numerous technological advances made during the past three years in the design, fabrication, and testing of the ISV process are discussed. Performance analysis of ISV focuses on process equipment, element retention (in the vitrified soil during processing), melt geometry, depth monitors, and electrodes. The types of soil and waste processed by ISV are evaluated as process parameters. Economic data provide the production costs of the large-scale unit for radioactive and hazardous chemical wastes (wet and dry). The processing of transuranic-contaminated soils are discussed with respect to occupational and public safety. Alternative applications and operating sequences for various waste sites are identified. The technological data base warrants conducting a large-scale radioactive test at a contaminated soil site at Hanford to provide a representative waste form that can be evaluated to determine its suitability for in-place stabilization of transuranic-contaminated soils.
Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented
FY-1981 project status for the Transuranic Waste Treatment Facility

International Nuclear Information System (INIS)

Benedetti, R.L.; Tait, T.D.

1981-11-01

The primary objective of the Transuranic Waste Treatment Facility (TWTF) Project is to provide a facility to process low-level transuranic waste stored at the Idaho National Engineering Laboratory (INEL) into a form acceptable for disposal at the Waste Isolation Pilot Plant. This report provides brief summary descriptions of the project objectives and background, project status through FY-1981, planned activities for FY-1982, and the EG and G TWTF Project office position on processing INEL transuranic waste
224-T Transuranic Waste Storage and Assay Facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-01-01

Westinghouse Hanford Company is a major contractor to the US Department of Energy Richland Field Office and serves as cooperator of the 224-T Transuranic Waste Storage and Assay Facility, the storage unit addressed in this permit application. At the time of submission of this portion of the Hanford Facility. Dangerous Waste Permit Application covering the 224-T Transuranic Waste Storage and Assay Facility, many issues identified in comments to the draft Hanford Facility Dangerous Waste Permit remain unresolved. This permit application reflects the positions taken by the US Department of Energy, Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application (Revision 0) consists of both a Part A and Part B permit application. An explanation of the Part A revisions associated with this unit, including the Part A revision currently in effect, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application contains information current as of March 1, 1992
Pre-1970 transuranic solid waste at the Hanford Site

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1995-01-01

The document is based on a search of pre-1970 Hanford Solid Waste Records. The available data indicates seven out of thirty-one solid waste burial sites used for pre-1970 waste appear to be Transuranic (TRU). A burial site defined to be TRU contains >100 nCi/gm Transuranic nuclides
Hanford site transuranic waste certification plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)
Incorporation of transuranic elements in titanate nuclear waste ceramics

International Nuclear Information System (INIS)

Matzke, H.J.; Ray, I.L.F.; Theile, H.; Trisoglio, C.; Walker, C.T.; White, T.J.

1990-01-01

The incorporation of actinide elements and their rare-earth element analogues in titanate nuclear waste forms in reviewed. New partitioning data are presented for three waste forms containing Purex waste simulant in combination with either NpO 2 , PuO 2 , or Am 2 O 3 . The greater proportion of transuranics partition between perovskite and zirconolite, while some americium may enter loveringite. Autoradiography revealed clusters of plutonium atoms which have been interpreted as unreacted dioxide or sesquioxide. It is concluded that the solid-state behavior of transuranic elements in titanate waste forms is poorly understood, certainly not well enough to tailor a ceramic for the incorporation of waste from reprocessing of fast breeder reactor fuel in which transuranic species are more abundant than in Purex waste
Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

2005-01-01

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

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions LLC

2005-12-29

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
Expert system for transuranic waste assay

Energy Technology Data Exchange (ETDEWEB)

Zoolalian, M.L.; Gibbs, A.; Kuhns, J.D.

1989-01-01

Transuranic wastes are generated at the Savannah River Site (SRS) as a result of routine production of nuclear materials. These wastes contain Pu-238 and Pu-239 and are placed into lined 55-gallon waste drums. The drums are placed on monitored storage pads pending shipment to the Waste Isolation Pilot Plant in New Mexico. A passive-active neutron (PAN) assay system is used to determine the mass of the radioactive material within the waste drums. Assay results are used to classify the wastes as either low-level or transuranic (TRU). During assays, the PAN assay system communicates with an IBM-AT computer. A Fortran computer program, called NEUT, controls and performs all data analyses. Unassisted, the NEUT program cannot adequately interpret assay results. To eliminate this limitation, an expert system shell was used to write a new algorithm, called the Transuranic Expert System (TRUX), to drive the NEUT program and add decision making capabilities for analysis of the assay results. The TRUX knowledge base was formulated by consulting with human experts in the field of neutron assay, by direct experimentation on the PAN assay system, and by observing operations on a daily basis. TRUX, with its improved ability to interpret assay results, has eliminated the need for close supervision by a human expert, allowing skilled technicians to operate the PAN assay system. 4 refs., 1 fig., 4 tabs.
Expert system for transuranic waste assay

International Nuclear Information System (INIS)

Zoolalian, M.L.; Gibbs, A.; Kuhns, J.D.

1989-01-01

Transuranic wastes are generated at the Savannah River Site (SRS) as a result of routine production of nuclear materials. These wastes contain Pu-238 and Pu-239 and are placed into lined 55-gallon waste drums. The drums are placed on monitored storage pads pending shipment to the Waste Isolation Pilot Plant in New Mexico. A passive-active neutron (PAN) assay system is used to determine the mass of the radioactive material within the waste drums. Assay results are used to classify the wastes as either low-level or transuranic (TRU). During assays, the PAN assay system communicates with an IBM-AT computer. A Fortran computer program, called NEUT, controls and performs all data analyses. Unassisted, the NEUT program cannot adequately interpret assay results. To eliminate this limitation, an expert system shell was used to write a new algorithm, called the Transuranic Expert System (TRUX), to drive the NEUT program and add decision making capabilities for analysis of the assay results. The TRUX knowledge base was formulated by consulting with human experts in the field of neutron assay, by direct experimentation on the PAN assay system, and by observing operations on a daily basis. TRUX, with its improved ability to interpret assay results, has eliminated the need for close supervision by a human expert, allowing skilled technicians to operate the PAN assay system. 4 refs., 1 fig., 4 tabs
The Los Alamos National Laboratory Transuranic Waste Retireval Project

International Nuclear Information System (INIS)

Montoya, G.M.; Christensen, D.V.; Stanford, A.R.

1997-01-01

This paper presents the status of the Los Alamos National Laboratory (LANL) project for remediation of transuranic (TRU) and TRU mixed waste from Pads 1, 2, and 4. Some of the TRU waste packages retrieved from Pad I are anticipated to be part of LANL's initial inventory to be shipped to the Waste Isolation Pilot Plant (WIPP) in April 1998. The TRU Waste Inspectable Storage Project (TWISP) was initiated in February 1993 in response to the New Mexico Environment Department's (NMED's) Consent Agreement for Compliance Order, ''New Mexico Hazardous Waste Agreement (NMHWA) 93-03.'' The TWISP involves the recovery of approximately 16,865 TRU and TRU-mixed waste containers currently under earthen cover on Pads 1, 2, and 4 at Technical Area 54, Area G, and placement of that waste into inspectable storage. All waste will be moved into inspectable storage by September 30, 2003. Waste recovery and storage operations emphasize protection of worker safety, public health, and the environment
Oak Ridge National Laboratory Transuranic Waste Certification Program

International Nuclear Information System (INIS)

Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

1988-08-01

The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs
Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Summary

International Nuclear Information System (INIS)

1997-05-01

This Waste Management Programmatic Environmental Impact Statement (WM PEIS) is a nationwide study examining the environmental impacts of managing five types of radioactive and hazardous wastes generated by past and future nuclear defense and research activities at a variety of sites located around the United States. The five waste types are low-level mixed waste (LLMW), low-level waste (LLW), transuranic waste (TRUW), high-level waste (HLW), and hazardous waste (HW)

National transuranic program plan

International Nuclear Information System (INIS)

1994-01-01

As a result of various program initiatives, the U.S. generated and will continue to generate waste contaminated with radioactive materials. Because of increased awareness of the risks and special requirements to safely manage long-lived alpha-emitting radionuclides, a new category of radioactive waste, transuranic (TRU) waste, was adopted in 1970. Heads of Field Elements can determine that other alpha-contaminated wastes, peculiar to a specific site, must be managed as transuranic wasteclose quotes. TRU waste is generated and stored at various DOE sites around the country. In December 1993, the National Transuranic Program Office (NTPO) was established as part of the Carlsbad Area Office (CAO) to integrate and coordinate the diverse organizational elements that contribute to the complex-wide management of TRU waste. Numerous sites with small TRU waste inventories are also part of the national TRU waste system. The majority of TRU waste is also contaminated with hazardous materials and is thus considered mixed waste. Mixed waste must be managed in compliance with all federal, state, and local regulations that are applicable to the radioactive and/or hazardous component of the waste. Each generator site is responsible for the management of its respective waste. Sites must plan and implement programs to minimize, characterize, package, treat, store, ship, and dispose of all TRU waste; construct required waste management facilities and equipment; obtain permits; perform site-specific National Environmental Policy Act (NEPA) analyses; conduct environmental studies; perform laboratory analyses; and certify that waste meets appropriate disposal facility criteria. Due to the toxicity and long half-lives of TRU radionuclides, TRU waste must be disposed in a manner that offers greater confinement than shallow land burial
Storage of transuranic contaminated solid wastes at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wehmann, George

1975-01-01

The storage method for low-level transuranic wastes employed at the Idaho National Engineering Laboratory is discussed in detail. The techniques used for wastes containing greater than ten nanocuries of transuranic material per gram of waste as well as the technique for lesser concentrations of transuranic wastes are described. The safety, efficiency and adequacy of these storage methods are presented
Final Hanford Site Transuranic (TRU) Waste Characterization Quality Assurance Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP
Assessment of allowable transuranic activity levels for WIPP wastes

International Nuclear Information System (INIS)

1987-12-01

This study provides a technical evaluation for the establishment of an upper limit on the transuranic content of waste packages to be received. To accomplish this, the predicted radiological performance of WIPP is compared to the radiological performance requirements applicable to WIPP. These performance requirements include radiation protection standards for both routine facility operations and credible operational accidents. These requirements are discussed in Chapter 2.0. From the margin between predicted performance and the performance requirements, the maximum allowable transuranic content of waste packages can then be inferred. Within the resulting compliance envelope, a waste acceptance criterion can be established that delineates the allowable level of transuranic radioactivity content for contact handled (CH) and remote handled (RH) waste packages. 13 refs., 8 tabs
Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1

International Nuclear Information System (INIS)

1997-01-01

This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste
US Department of Energy acceptance of commercial transuranic waste

International Nuclear Information System (INIS)

Taboas, A.L.; Bennett, W.S.; Brown, C.M.

1980-02-01

Contaminated transuranic wastes generated as a result of non-defense activities have been disposed of by shallow land burial at a commercially operated (NECO) facility located on the Hanford federal reservation, which is licensed by the State of Washington and by the NRC. About 15,000 ft 3 of commercial TRU waste have been generated each year, but generation for the next three years could triple due to decontamination and decommissioning scheduled to start in 1980. Disposal at other commercial burial sites has been precluded due to sites closing or prohibitions on acceptance of transuranic wastes. The State of Washington recently modified the NECO-Hanford operating license, effective February 29, 1980, to provide that radioactive wastes contaminated with transuranics in excess of 10 nCi/g will not be accepted for disposal. Consistent with the state policy, the NRC amended the NECO special nuclear material license so that Pu in excess of 10n Ci/g cannot be accepted after February 29, 1980. As a result, NRC requested DOE to examine the feasibility of accepting these wastes at a DOE operated site. TRU wastes accepted by the DOE would be placed in retrievable storage in accordance with DOE policy which requires retrievable storage of transuranic wastes pending final disposition in a geologic repository. DOE transuranic wastes are stored at six major DOE sites: INEL, Hanford, LASL, NTS, ORNL, and SRP. A specific site for receiving commercial TRU waste has not yet been selected. Shipments to DOE-Hanford would cause the least disruption to past practices. Commercial TRU wastes would be subject to waste form and packaging criteria established by the DOE. The waste generators would be expected to incur all applicable costs for DOE to take ownership of the waste, and provide storage, processing, and repository disposal. The 1980 charge to generators for DOE acceptance of commercial TRU waste is $147 per cubic foot
Transuranic contaminated waste form characterization and data base

International Nuclear Information System (INIS)

Kniazewycz, B.G.; McArthur, W.C.

1980-07-01

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies
Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP)
Transuranic waste form characterization and data base. Executive summary

International Nuclear Information System (INIS)

1980-01-01

The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics
Characterization of transuranic solid wastes from a plutonium processing facility

International Nuclear Information System (INIS)

Mulkin, R.

1975-06-01

Transuranic-contaminated wastes generated in the processing areas of the Plutonium Chemistry and Metallurgy Group at the Los Alamos Scientific Laboratory (LASL) were studied in detail to identify their chemical and physical composition. Nondestructive Assay (NDA) equipment was developed to measure transuranic activity at the 10-nCi/g level in low-density residues typically found in room-generated waste. This information will supply the Waste Management Program with a more positive means of identifying concerns in waste storage and the challenge of optimizing the system of waste form, packaging, and environment of the storage area for 20-yr retrievable waste. A positive method of measuring transuranic activity in waste at the 10-nCi/g level will eliminate the need for administrative control in a sensitive area, and will provide the economic advantage of minimizing the volume of waste stored as retrievable waste. (U.S.)
Characterizing cemented TRU waste for RCRA hazardous constituents

International Nuclear Information System (INIS)

Yeamans, D.R.; Betts, S.E.; Bodenstein, S.A.

1996-01-01

Los Alamos National Laboratory (LANL) has characterized drums of solidified transuranic (TRU) waste from four major waste streams. The data will help the State of New Mexico determine whether or not to issue a no-migration variance of the Waste Isolation Pilot Plant (WIPP) so that WIPP can receive and dispose of waste. The need to characterize TRU waste stored at LANL is driven by two additional factors: (1) the LANL RCRA Waste Analysis Plan for EPA compliant safe storage of hazardous waste; (2) the WIPP Waste Acceptance Criteria (WAC) The LANL characterization program includes headspace gas analysis, radioassay and radiography for all drums and solids sampling on a random selection of drums from each waste stream. Data are presented showing that the only identified non-metal RCRA hazardous component of the waste is methanol
Transuranic Waste Characterization Quality Assurance Program Plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-30

This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.
Transuranic Waste Characterization Quality Assurance Program Plan

International Nuclear Information System (INIS)

1995-01-01

This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes
Optimizing transuranic waste management-challenges and opportunities

International Nuclear Information System (INIS)

Triay, I.R.; Wu, C.F.; Moody, D.C.; Jennings, S.G.

2002-01-01

The opening of the Waste Isolation Pilot Plant (WIPP) for disposal of transuranic (TRU) waste in March of 1999, the granting of the Hazardous Waste Facility Permit in November 1999, and over two years of operational experience have demonstrated the Department of Energy's (DOE'S) capability in closing the nuclear energy cycle. While these achievements resolved several scientific, engineering, regulatory and political issues, the DOE has identified a new set of challenges that represent opportunities for improving programmatic efficiency, cost-effectiveness, and operational safety in managing the nation's TRU waste. The DOE has recognized that the complex administrative and regulatory requirements for characterization, transportation and disposal of TRU waste are costly (1). A review by the National Academy of Sciences (NAS) states that these requirements lead to inefficient waste characterization, handling and transportation operations that in turn can lead to unnecessary radiation exposure to workers without a commensurate decrease in risk to the public and the environment (2). This paper provides an overview of the status of the WJPP repository, explains the principles of the proposed commercial business approach, and describes some of the proposed major enhancements of the TRU waste transportation systems. The DOE is developing a remote-handled (RH) waste program to enable emplacement of RH waste at WPP. This program includes appropriate facility modifications and regulatory changes (3).
Transuranic Solid Waste Management Programs. Progress report, July--December 1974

International Nuclear Information System (INIS)

1975-10-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory by the Energy Research and Development Administration Division of Waste Management and Transportation. Under the Transuranic Waste Research and Development Program, a completed evaluation of stainless steel drums showed that although the material has superior corrosion-resistant properties, its higher cost makes a thorough investigation of other container systems mandatory. A program to investigate more economical, nonmetallic containers is proposed. Preliminary fire tests in mild steel drums have been completed with fire propagation not appearing to be a problem unless container integrity is lost. Investigation of the corrosion of mild steel drums and the evaluation of potential corrosion inhibitors, in a variety of humid environments, continues. Experimental results of both laboratory and field investigations on radiolysis of transuranic elements in hydrogenous waste are discussed. Progress in the development of instrumentation for monitoring and segregating low-level wastes is described. New plans and developments for the Transuranic-Contaminated Solid Waste Treatment Development Facility are presented. The current focus is on a comparison of all alternative waste reduction systems toward a relative Figure of Merit with universal application. Drawings, flowsheets, and building layouts are included, and the proposed incinerator device is detailed. The release mechanisms, inter- and intraregional transport mechanisms, and exhumation studies relevant to the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas Program are defined and analyzed. A detailed description is given of the formulation of the computer simulation scheme for the intraregional biological transport model
Processing and certification of defense transuranic waste at the INEL

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cargo, C.H.; McKinley, K.B.; Smith, T.H.; Anderson, B.C.

1984-01-01

Since 1970, defense-generated transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the US Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste form the INEL. To support this objective, the Stored Waste Examination Pilot Plant (SWEPP) and the Process Experimental Pilot Plant (PREPP) are currently being constructed. SWEPP will certify waste, using nondestructive examination techniques, for shipment to the Waste Isolation Pilot Plant (WIPP). PREPP will process uncertifiable waste into a certifiable waste form. 3 references
Hanford Site Transuranic (TRU) Waste Certification Plan

Energy Technology Data Exchange (ETDEWEB)

GREAGER, T.M.

1999-09-09

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.
Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP
Transuranic waste baseline inventory report. Revision No. 3

International Nuclear Information System (INIS)

1996-06-01

The Transuranic Waste Baseline Inventory Report (TWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties from across the U.S. Department of Energy (DOE) transuranic (TRU) waste system into a series of open-quotes waste profilesclose quotes that can be used as the basis for waste form discussions with regulatory agencies. The purpose of Revisions 0 and 1 of this report was to provide data to be included in the Sandia National Laboratories/New Mexico (SNL/NM) performance assessment (PA) processes for the Waste Isolation Pilot Plant (WIPP). Revision 2 of the document expanded the original purpose and was also intended to support the WIPP Land Withdrawal Act (LWA) requirement for providing the total DOE TRU waste inventory. The document included a chapter and an appendix that discussed the total DOE TRU waste inventory, including nondefense, commercial, polychlorinated biphenyls (PCB)-contaminated, and buried (predominately pre-1970) TRU wastes that are not planned to be disposed of at WIPP
Waste management facilities cost information for transuranic waste

International Nuclear Information System (INIS)

Shropshire, D.; Sherick, M.; Biagi, C.

1995-06-01

This report contains preconceptual designs and planning level life-cycle cost estimates for managing transuranic waste. The report's information on treatment and storage modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the U.S. Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report

Developing an institutional strategy for transporting defense transuranic waste materials

International Nuclear Information System (INIS)

Guerrero, J.V.; Kresny, H.S.

1986-01-01

In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key to the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations
The Transuranic Waste Program's integration and planning activities and the contributions of the TRU partnership

International Nuclear Information System (INIS)

Harms, T.C.; O'Neal, W.; Petersen, C.A.; McDonald, C.E.

1994-02-01

The Technical Support Division, EM-351 manages the integration and planning activities of the Transuranic Waste Program. The Transuranic Waste Program manager provides transuranic waste policy, guidance, and issue resolution to Headquarters and the Operations Offices. In addition, the program manager is responsible for developing and implementing an integrated, long-range waste management plan for the transuranic waste system. A steering committee, a core group of support contractors, and numerous interface working groups support the efforts of the program manager. This paper provides an overview of the US Department of Energy's transuranic waste integration activities and a long-range planning process that includes internal and external stakeholder participation. It discusses the contributions and benefits provided by the Transuranic Partnership, most significantly, the integration activities and the body of data collected and assembled by the Partnership
Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

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
Reliability evaluation methodologies for ensuring container integrity of stored transuranic (TRU) waste

International Nuclear Information System (INIS)

Smith, K.L.

1995-06-01

This report provides methodologies for providing defensible estimates of expected transuranic waste storage container lifetimes at the Radioactive Waste Management Complex. These methodologies can be used to estimate transuranic waste container reliability (for integrity and degradation) and as an analytical tool to optimize waste container integrity. Container packaging and storage configurations, which directly affect waste container integrity, are also addressed. The methodologies presented provide a means for demonstrating Resource Conservation and Recovery Act waste storage requirements
Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

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

International Nuclear Information System (INIS)

1995-02-01

This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database
Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 1. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-02-01

This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database.
Economic comparison of centralizing or decentralizing processing facilities for defense transuranic waste

International Nuclear Information System (INIS)

Brown, C.M.

1980-07-01

This study is part of a set of analyses under direction of the Transuranic Waste Management Program designed to provide comprehensive, systematic methodology and support necessary to better understand options for national long-term management of transuranic (TRU) waste. The report summarizes activities to evaluate the economics of possible alternatives in locating facilities to process DOE-managed transuranic waste. The options considered are: (1) Facilities located at all major DOE TRU waste generating sites. (2) Two or three regional facilities. (3) Central processing facility at only one DOE site. The study concludes that processing at only one facility is the lowest cost option, followed, in order of cost, by regional then individual site processing
The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

International Nuclear Information System (INIS)

Ross, W.A.; Kindle, C.H.

1992-06-01

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity
Economic evaluation of volume reduction for Defense transuranic waste

International Nuclear Information System (INIS)

Brown, C.M.

1982-03-01

The economics of volume reduction of retrievably stored and newly generated DOE transuranic wastes are evaluated by comparing the costs of reduction of the wastes with the savings possible in transportation and disposal. A general approach to the comparison of TRU waste volume reduction costs and cost savings is developed, an initial set of cost data is established, conclusions to support selecting technologies and facilities for the disposal of DOE transuranic waste are developed. Section I outlines the analysis which considers seven types of volume reduction from incineration and compaction of combustibles to compaction, size reduction, shredding, melting, and decontamination of metals. The study considers the volume reduction of contact-handled, newly generated and retrievably stored DOE transuranic wastes. Section II of this report describes the analytical approach, assumptions, and flow of waste material through sites. Section III presents the waste inventories, disposal and transportation savings, and volume reduction techniques and costs. Section IV contains the results and conclusions of the study. The major conclusions drawn from the study are: For DOE sites with a small amount of waste requiring disposal ( 3 /year) the cost of volume reduction is greater than the transportation and disposal savings from volume reduction provided the waste requires little additional preparation to meet transportation and disposal criteria. Wastes that do not meet these criteria require site specific economic analysis outside the general evaluations of this study. For Idaho National Engineering Laboratory, incineration and metal shredding are cost-effective, provided a facility is to be constructed as a consequence of repackaging the fraction of stored waste which may require repackaging and immobilizing chemical process waste to meet disposal criteria
Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

International Nuclear Information System (INIS)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m 3 /MTU for no treatment to as low as 0.02 m 3 /MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs
Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

Energy Technology Data Exchange (ETDEWEB)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.
Controlled-air incineration of transuranic-contaminated solid waste

International Nuclear Information System (INIS)

Borduin, L.C.; Draper, W.E.; Koenig, R.A.; Neuls, A.S.; Warner, C.L.

1976-01-01

A controlled-air incinerator and an associated high-energy aqueous off-gas cleaning system are being installed at the Los Alamos Scientific Laboratory (LASL) Transuranic Waste Treatment Development Facility (TDF) for evaluation as a low-level transuranic-contaminated (TRU) solid waste volume reduction process. Program objectives are: (1) assembly and operation of a production scale (45 kg/hr) operation of ''off-the-shelf'' components representative of current incineration and pollution control technology; (2) process development and modification to meet radioactive health and safety standards, and (3) evaluation of the process to define the advantages and limitations of conventional technology. The results of the program will be the design specifications and operating procedures necessary for successful incineration of TRU waste. Testing, with nonradioactive waste, will begin in October 1976. This discussion covers commercially available incinerator and off-gas cleaning components, the modifications required for radioactive service, process components performance expectations, and a description of the LASL experimental program
Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1991-07-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location
Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1993-01-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location
Projected transuranic waste loads requiring treatment, storage, and disposal

International Nuclear Information System (INIS)

Hong, K.; Kotek, T.

1996-01-01

This paper provides information on the volume of TRU waste loads requiring treatment, storage, and disposal at DOE facilities for three siting configurations. Input consisted of updated inventory and generation data from. Waste Isolation Pilot plant Transuranic Waste Baseline Inventory report. Results indicate that WIPP's design capacity is sufficient for the CH TRU waste found throughout the DOE Complex
2016 Los Alamos National Laboratory Hazardous Waste Minimization Report

Energy Technology Data Exchange (ETDEWEB)

Salzman, Sonja L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); English, Charles Joe [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-12-02

Waste minimization and pollution prevention are goals within the operating procedures of Los Alamos National Security, LLC (LANS). The US Department of Energy (DOE), inclusive of the National Nuclear Security Administration (NNSA) and the Office of Environmental Management, and LANS are required to submit an annual hazardous waste minimization report to the New Mexico Environment Department (NMED) in accordance with the Los Alamos National Laboratory (LANL or the Laboratory) Hazardous Waste Facility Permit. The report was prepared pursuant to the requirements of Section 2.9 of the LANL Hazardous Waste Facility Permit. This report describes the hazardous waste minimization program, which is a component of the overall Pollution Prevention (P2) Program, administered by the Environmental Stewardship Group (EPC-ES). This report also supports the waste minimization and P2 goals of the Associate Directorate of Environmental Management (ADEM) organizations that are responsible for implementing remediation activities and describes its programs to incorporate waste reduction practices into remediation activities and procedures. This report includes data for all waste shipped offsite from LANL during fiscal year (FY) 2016 (October 1, 2015 – September 30, 2016). LANS was active during FY2016 in waste minimization and P2 efforts. Multiple projects were funded that specifically related to reduction of hazardous waste. In FY2016, there was no hazardous, mixed-transuranic (MTRU), or mixed low-level (MLLW) remediation waste shipped offsite from the Laboratory. More non-remediation hazardous waste and MLLW was shipped offsite from the Laboratory in FY2016 compared to FY2015. Non-remediation MTRU waste was not shipped offsite during FY2016. These accomplishments and analysis of the waste streams are discussed in much more detail within this report.
Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume III of V

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type
Waste management facilities cost information for transportation of radioactive and hazardous materials

International Nuclear Information System (INIS)

Feizollahi, F.; Shropshire, D.; Burton, D.

1995-06-01

This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled ( 200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations
Waste management facilities cost information for transportation of radioactive and hazardous materials

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Shropshire, D.; Burton, D.

1995-06-01

This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled (<200 mrem/hr contact dose) and remote-handled (>200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations.

In situ vitrification: application analysis for stabilization of transuranic waste

International Nuclear Information System (INIS)

Oma, K.H.; Farnsworth, R.K.; Rusin, J.M.

1982-09-01

The in situ vitrification process builds upon the electric melter technology previously developed for high-level waste immobilization. In situ vitrification converts buried wastes and contaminated soil to an extremely durable glass and crystalline waste form by melting the materials, in place, using joule heating. Once the waste materials have been solidified, the high integrity waste form should not cause future ground subsidence. Environmental transport of the waste due to water or wind erosion, and plant or animal intrusion, is minimized. Environmental studies are currently being conducted to determine whether additional stabilization is required for certain in-ground transuranic waste sites. An applications analysis has been performed to identify several in situ vitrification process limitations which may exist at transuranic waste sites. Based on the process limit analysis, in situ vitrification is well suited for solidification of most in-ground transuranic wastes. The process is best suited for liquid disposal sites. A site-specific performance analysis, based on safety, health, environmental, and economic assessments, will be required to determine for which sites in situ vitrification is an acceptable disposal technique. Process economics of in situ vitrification compare favorably with other in-situ solidification processes and are an order of magnitude less than the costs for exhumation and disposal in a repository. Leachability of the vitrified product compares closely with that of Pyrex glass and is significantly better than granite, marble, or bottle glass. Total release to the environment from a vitrified waste site is estimated to be less than 10 -5 parts per year. 32 figures, 30 tables
Acceptable knowledge document for INEEL stored transuranic waste - Rocky Flats Plant waste. Revision 2

International Nuclear Information System (INIS)

1998-01-01

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-23

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.
Transportation system (TRUPACT) for contact-handled transuranic wastes

International Nuclear Information System (INIS)

Romesberg, L.E.; Pope, R.B.; Burgoyne, R.M.

1982-04-01

Contact-handled transuranic defense waste is being, and will continue to be, moved between a number of locations in the United States. The DOE is sponsoring development of safe, efficient, licensable, and cost-effective transportation systems to handle this waste. The systems being developed have been named TRUPACT which stands for TRansUranic PACkage Transporter. The system will be compatible with Type A packagings used by waste generators, interim storage facilities, and repositories. TRUPACT is required to be a Type B packaging since larger than Type A quantities of some radionuclides (particularly plutonium) may be involved in the collection of Type A packagings. TRUPACT must provide structural and thermal protection to the waste in hypothetical accident environments specified in DOT regulations 49CFR173 and NRC regulations 10CFR71. Preliminary design of the systems has been completed and final design for a truck system is underway. The status of the development program is reviewed in this paper and the reference design is described. Tests that have been conducted are discussed and long-term program objectives are reviewed
Los Alamos transuranic waste size reduction facility

International Nuclear Information System (INIS)

Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

1982-01-01

To facilitate disposal of transuranic (TRU) waste, Los Alamos National Laboratory designed and constructed the Size Reduction Facility (SRF) during the period 1977 to 1981. This report summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes
Los Alamos transuranic waste size reduction facility

International Nuclear Information System (INIS)

Briesmeister, A.; Harper, J.; Reich, B.; Warren, J.L.

1982-01-01

A transuranic (TRU) Waste Size Reduction Facility (SRF) was designed and constructed at the Los Alamos National Laboratory during the period of 1977 to 1981. This paper summarizes the engineering development, installation, and early test operations of the SRF. The facility incorporates a large stainless steel enclosure fitted with remote handling and cutting equipment to obtain an estimated 4:1 volume reduction of gloveboxes and other bulky metallic wastes
Long-lived legacy: Managing high-level and transuranic waste at the DOE Nuclear Weapons Complex. Background paper

International Nuclear Information System (INIS)

1991-05-01

The document focuses on high-level and transuranic waste at the DOE nuclear weapons complex. Reviews some of the critical areas and aspects of the DOE waste problem in order to provide data and further analysis of important issues. Partial contents, High-Level Waste Management at the DOE Weapons Complex, are as follows: High-Level Waste Management: Present and Planned; Amount and Distribution; Current and Potential Problems; Vitrification; Calcination; Alternative Waste Forms for the Idaho National Engineering Laboratory; Technologies for Pretreatment of High-Level Waste; Waste Minimization; Regulatory Framework; Definition of High-Level Waste; Repository Delays and Contingency Planning; Urgency of High-Level Tank Waste Treatment; Technologies for High-Level Waste Treatment; Rethinking the Waste Form and Package; Waste Form for the Idaho National Engineering Laboratory; Releases to the Atmosphere; Future of the PUREX Plant at Hanford; Waste Minimization; Tritium Production; International Cooperation; Scenarios for Future HLW Production. Partial contents of Chapter 2, Managing Transuranic Waste at the DOE Nuclear Weapons Complex, are as follows: Transuranic Waste at Department of Energy Sites; Amount and Distribution; Waste Management: Present and Planned; Current and Potential Problems; Three Technologies for Treating Retrievably Stored Transuranic Waste; In Situ Vitrification; The Applied Research, Development, Demonstration, Testing, and Evaluation Plan (RDDT ampersand E); Actinide Conversion (Transmutation); Waste Minimization; The Regulatory Framework; Definition of, and Standards for, Disposal of Transuranic Waste; Repository Delays; Alternative Storage and Disposal Strategies; Remediation of Buried Waste; The Waste Isolation Pilot Plant; Waste Minimization; Scenarios for Future Transuranic Waste Production; Conditions of No-Migration Determination
Chemical laboratory hazardous waste management at a DOE multiprogram national laboratory

International Nuclear Information System (INIS)

Turner, P.J.

1990-03-01

Pacific Northwest Laboratory (PNL), a United States Department of Energy (DOE) Multiprogram Energy Laboratory, is establishing a program for management of diverse small-quantity laboratory waste generated on site. Although the main emphasis of this program is ''cradle-to-grave'' tracking and treatment of hazardous chemical waste and mixed waste, low-level radioactive and transuranic (TRU) waste is also being included. With the program in operation, more than 95% of all regulated waste will be treated or destroyed on site. The cost savings will return the original investment in under six years and decrease the liability to PNL and DOE -- a benefit with a potentially greater economic value. Tracking of hazardous waste will be mediated by a computer-based inventory and tracking system. The system will track all hazardous materials from receipt through final disposition, whether the material is destroyed or treated for disposal. It will allow user access to handling and hazards information as well as provide an updated inventory by location, user, and hazard type. Storage and treatment of waste will be performed by at least four facilities, made operational in three phases. 6 figs
Approach for systematic evaluation of transuranic waste management alternatives

International Nuclear Information System (INIS)

Hong, K.; Koebnick, B.; Kotek, T.

1994-01-01

This paper describes an approach for systematic evaluation of management alternatives that are being considered for the treatment, storage, and disposal of transuranic waste (TRUW) at U.S. Department of Energy sites. The approach, which is currently under development, would apply WASTE-MGMT, a database application model developed at Argonne National Laboratory, to estimate projected environmental releases and would evaluate impact measures such as health risk and costs associated with each of the waste management alternatives. The customized application would combine site-specific TRUW inventory and characterization data with treatment and transportation parameters to estimate the quantities and characteristics of the wastes to be treated, emissions of hazardous substances from the treatment facilities, and the quantities and characteristics of the wastes to be shipped between sites. These data would then be used to estimate for several TRUW management scenarios the costs and health risks of constructing and operating the required treatment facilities and of transporting TRUW for treatment and final disposal. Treatment, storage, and disposal of TRUW at DOE sites is composed of many variables and options at each stage. The approach described in this paper would provide for efficient consideration of all of these facets when evaluating potentially feasible TRUW management alternatives. By expanding existing databases, this model could eventually be adapted to accommodate the introduction of new treatment technologies, updated TRUW characterization data, and/or revised waste acceptance criteria
Integration of long-range planning for management of defense transuranic waste

International Nuclear Information System (INIS)

Gilbert, K.V.; McFadden, M.H.; Raudenbush, M.H.; Smith, L.J.

1984-01-01

As described in The Defense Waste Management Plan, the defense TRU program goal is to achieve permanent disposal and to end interim storage. TRU waste is currently stored at six Department of Energy (DOE) sites, and new waste is generated at several more sites. The Waste Isolation Pilot Plant (WIPP) project is well defined, and it has been necessary to integrate the activities of other parts of the TRU program in support of DOE Headquarters policy and the WIPP schedules and technical requirements. The strategy is described in the Defense Transuranic Waste Program Strategy Document. More detailed, quantitative plans have been developed through the use of several system models, with a Long-Range Master Plan for Defense Transuranic Waste Management as the focal point for coordination of proposed plans with all the parties involved
Controlled air incineration of hazardous chemical waste at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stretz, L.A.; Borduin, L.C.; Draper, W.E.; Koenig, R.A.; Vavruska, J.S.

1982-01-01

An incineration system, originally demonstrated as a transuranic (TRU) waste volume-reduction process, is described. The production-scale controlled air incinerator using commercially available equipment and technology was modified for solid radioactive waste service. The same incinerator and offgas treatment system has been modified further for use in evaluating the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood. Results of a PCP-treated wood incineration test show a PCP destruction efficiency of greater than 99.99% in the primary chamber for the operating conditions investigated. Conditions and results for this test are described
Apparatus for incinerating hazardous waste

Science.gov (United States)

Chang, R.C.W.

1994-12-20

An apparatus is described for incinerating wastes, including an incinerator having a combustion chamber, a fluid-tight shell enclosing the combustion chamber, an afterburner, an off-gas particulate removal system and an emergency off-gas cooling system. The region between the inner surface of the shell and the outer surface of the combustion chamber forms a cavity. Air is supplied to the cavity and heated as it passes over the outer surface of the combustion chamber. Heated air is drawn from the cavity and mixed with fuel for input into the combustion chamber. The pressure in the cavity is maintained at least approximately 2.5 cm WC higher than the pressure in the combustion chamber. Gases cannot leak from the combustion chamber since the pressure outside the chamber (inside the cavity) is higher than the pressure inside the chamber. The apparatus can be used to treat any combustible wastes, including biological wastes, toxic materials, low level radioactive wastes, and mixed hazardous and low level transuranic wastes. 1 figure.
Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume I of V

International Nuclear Information System (INIS)

1997-05-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for treated (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the no action alternative, which includes only existing or approved waste management facilities, the alternatives for each of the waste type configurations include decentralized, regionalized, and centralized alternatives for using existing and operating new waste management facilities. However, the siting, construction and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review
Unresolved issues for the disposal of remote-handled transuranic waste in the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Silva, M.K.; Neill, R.H.

1994-09-01

The purpose of the Waste Isolation Pilot Plant (WIPP) is to dispose of 176,000 cubic meters of transuranic (TRU) waste generated by the defense activities of the US Government. The envisioned inventory contains approximately 6 million cubic feet of contact-handled transuranic (CH TRU) waste and 250,000 cubic feet of remote handled transuranic (RH TRU) waste. CH TRU emits less than 0.2 rem/hr at the container surface. Of the 250,000 cubic feet of RH TRU waste, 5% by volume can emit up to 1,000 rem/hr at the container surface. The remainder of RH TRU waste must emit less than 100 rem/hr. These are major unresolved problems with the intended disposal of RH TRU waste in the WIPP. (1) The WIPP design requires the canisters of RH TRU waste to be emplaced in the walls (ribs) of each repository room. Each room will then be filled with drums of CH TRU waste. However, the RH TRU waste will not be available for shipment and disposal until after several rooms have already been filled with drums of CH TRU waste. RH TRU disposal capacity will be loss for each room that is first filled with CH TRU waste. (2) Complete RH TRU waste characterization data will not be available for performance assessment because the facilities needed for waste handling, waste treatment, waste packaging, and waste characterization do not yet exist. (3) The DOE does not have a transportation cask for RH TRU waste certified by the US Nuclear Regulatory Commission (NRC). These issues are discussed along with possible solutions and consequences from these solutions. 46 refs
Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

Energy Technology Data Exchange (ETDEWEB)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable.
Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable
Nondestructive characterization of low-level transuranic waste

International Nuclear Information System (INIS)

Barna, B.A.; Reinhardt, W.W.

1981-10-01

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year effort designed to yield a production waste characterization system
Bioprocessing of low-level radioactive and mixed hazard wastes

International Nuclear Information System (INIS)

Stoner, D.L.

1990-01-01

Biologically-based treatment technologies are currently being developed at the Idaho National Engineering Laboratory (INEL) to aid in volume reduction and/or reclassification of low-level radioactive and mixed hazardous wastes prior to processing for disposal. The approaches taken to treat low-level radioactive and mixed wastes will reflect the physical (e.g., liquid, solid, slurry) and chemical (inorganic and/or organic) nature of the waste material being processed. Bioprocessing utilizes the diverse metabolic and biochemical characteristics of microorganisms. The application of bioadsorption and bioflocculation to reduce the volume of low-level radioactive waste are strategies comparable to the use of ion-exchange resins and coagulants that are currently used in waste reduction processes. Mixed hazardous waste would require organic as well as radionuclide treatment processes. Biodegradation of organic wastes or bioemulsification could be used in conjunction with radioisotope bioadsorption methods to treat mixed hazardous radioactive wastes. The degradation of the organic constituents of mixed wastes can be considered an alternative to incineration, while the use of bioemulsification may simply be used as a means to separate inorganic and organics to enable reclassification of wastes. The proposed technology base for the biological treatment of low-level radioactive and mixed hazardous waste has been established. Biodegradation of a variety of organic compounds that are typically found in mixed hazardous wastes has been demonstrated, degradative pathways determined and the nutritional requirements of the microorganisms are understood. Accumulation, adsorption and concentration of heavy and transition metal species and transuranics by microorganisms is widely recognized. Work at the INEL focuses on the application of demonstrated microbial transformations to process development
Assessment of gas flammability in transuranic waste container

International Nuclear Information System (INIS)

Connolly, M.J.; Loehr, C.A.; Djordjevic, S.M.; Spangler, L.R.

1995-01-01

The Safety Analysis Report for the TRUPACT-II Shipping Package [Transuranic Package Transporter-II (TRUPACT-II) SARP] set limits for gas generation rates, wattage limits, and flammable volatile organic compound (VOC) concentrations in transuranic (TRU) waste containers that would be shipped to the Waste Isolation Pilot Plant (WIPP). Based on existing headspace gas data for drums stored at the Idaho National Engineering Laboratory (INEL) and the Rocky Flats Environmental Technology Site (RFETS), over 30 percent of the contact-handled TRU waste drums contain flammable VOC concentrations greater than the limit. Additional requirements may be imposed for emplacement of waste in the WIPP facility. The conditional no-migration determination (NMD) for the test phase of the facility required that flame tests be performed if significant levels of flammable VOCs were present in TRU waste containers. This paper describes an approach for investigating the potential flammability of TRU waste drums, which would increase the allowable concentrations of flammable VOCS. A flammability assessment methodology is presented that will allow more drums to be shipped to WIPP without treatment or repackaging and reduce the need for flame testing on drums. The approach includes experimental work to determine mixture lower explosive limits (MLEL) for the types of gas mixtures observed in TRU waste, a model for predicting the MLEL for mixtures of VOCS, hydrogen, and methane, and revised screening limits for total flammable VOCs concentrations and concentrations of hydrogen and methane using existing drum headspace gas data and the model predictions
Utilization of borosilicate glass for transuranic waste immobilization

International Nuclear Information System (INIS)

Ledford, J.A.; Williams, P.M.

1979-01-01

Incinerated transuranic waste and other low-level residues have been successfully vitrified by mixing with boric acid and sodium carbonate and heating to 1050 0 C in a bench-scale continuous melter. The resulting borosilicate glass demonstrates excellent mechanical durability and chemical stability

Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume IV of V

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Transportation is an integral component of the alternatives being considered for each type of radioactive waste in the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The types of radioactive waste considered in Part I are high-level waste (HLW), low-level waste (LLW), transuranic waste (TRUW), and low-level mixed waste (LLMW). For some alternatives, radioactive waste would be shipped among the DOE sites at various stages of the treatment, storage, and disposal (TSD) process. The magnitude of the transportation-related activities varies with each alternative, ranging from minimal transportation for decentralized approaches to significant transportation for some centralized approaches. The human health risks associated with transporting various waste materials were assessed to ensure a complete appraisal of the impacts of each PEIS alternative being considered
Systems Engineering in the Development and Implementation of the Savannah River Site Transuranic Waste Disposition Program

International Nuclear Information System (INIS)

Fayfich, R.R.

1999-01-01

The use of systems engineering facilitated the strategic planning and implementation of the Savannah River Site (SRS) transuranic waste disposal program. This application represented the first SRS use of systems engineering in the pre-program planning stages during the development of a comprehensive strategic plan for the disposal of transuranic waste at the Department of Energy Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The use of systems engineering focused the efforts of the technical experts to devise a three initiative plan for the disposal of transuranic waste where previous efforts failed. Continued application of systems engineering facilitated the further development and implementation of the first initiative outlined in the strategic plan, i.e., set-up the program and process to begin to characterize and ship waste to the WIPP.This application of systems engineering to the transuranic waste program represented the first opportunity at the SRS for a comprehensive usage of systems engineering at all program levels. The application was initiated at the earliest possible point in the program development, i.e., strategic planning, and successively was used in detailed development and implementation of the program. Systems engineering successfully focused efforts to produce a comprehensive plan for the disposal of SRS transuranic waste at the WIPP, and facilitated development of the SRS capability and infrastructure to characterize, certify, and ship waste
Calculation of projected waste loads for transuranic waste management alternatives

International Nuclear Information System (INIS)

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

1995-01-01

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

International Nuclear Information System (INIS)

Slate, L.J.; Santee, G.E. Jr.

1996-01-01

This study documents preliminary scoping calculations to address criticality issues associated with the processing of transuranic (TRU) waste and TRU mixed waste in the Plasma Hearth Process (PHP) Test Project. To assess the criticality potential associated with processing TRU waste, the process flow in the PHP is evaluated to identify the stages where criticality could occur. A criticality analysis methodology is then formulated to analyze the criticality potential. Based on these analyses, TRU acceptance criteria can be defined for the PHP. For the current level of analysis, the methodology only assesses the physical system as designed and does not address issues associated with the criticality double contingency principle. The analyses suggest that criticality within the PHP system and within the planned treatment residue (stag) containers does not pose a criticality hazard even when processing waste feed drums containing a quantity of TRU greater than would be reasonably expected. The analyses also indicate that the quantity of TRU that can be processed during each batch is controlled by moving and storage conditions for the resulting slag collection drums
Methods for removing transuranic elements from waste solutions

International Nuclear Information System (INIS)

Slater, S.A.; Chamberlain, D.B.; Connor, C.; Sedlet, J.; Srinivasan, B.; Vandegrift, G.F.

1994-11-01

This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant
Hydrothermal processing of transuranic contaminated combustible waste

International Nuclear Information System (INIS)

Buelow, S.J.; Worl, L.; Harradine, D.; Padilla, D.; McInroy, R.

2001-01-01

Experiments at Los Alamos National Laboratory have demonstrated the usefulness of hydrothermal processing for the disposal of a wide variety of transuranic contaminated combustible wastes. This paper provides an overview of the implementation and performance of hydrothermal treatment for concentrated salt solutions, explosives, propellants, organic solvents, halogenated solvents, and laboratory trash, such as paper and plastics. Reaction conditions vary from near ambient temperatures and pressure to over 1000degC and 100 MPa pressure. Studies involving both radioactive and non-radioactive waste simulants are discussed. (author)
Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume V of V

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear energy research and the development, production, and testing of nuclear weapons at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives, which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for created (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the No Action Alternative, which includes only existing of approved waste management facilities, the alternatives for each of the waste-type configurations include Decentralized, Regionalized, and Centralized Alternatives for using existing and operating new waste management facilities. However, the siting, construction, and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review
Management of remote-handled defense transuranic wastes

International Nuclear Information System (INIS)

Ebra, M.A.; Pierce, G.D.; Carson, P.H.

1988-01-01

Transuranic (TRU) wastes generated by defense-related activities are scheduled for emplacement at the Waste Isolation Pilot Plant (WIPP) in New Mexico beginning in October 1988. After five years of operation as a research and development facility, the WIPP may be designated as a permanent repository for these wastes, if it has been demonstrated that this deep, geologically stable formation is a safe disposal option. Defense TRU wastes are currently stored at various Department of Energy (DOE) sites across the nation. Approximately 2% by volume of currently stored TRU wastes are defined, on the basis of dose rates, as remote-handled (RH). RH wastes continue to be generated at various locations operated by DOE contractors. They require special handling and processing prior to and during emplacement in the WIPP. This paper describes the strategy for managing defense RH TRU wastes
Shredder and incinerator technology for volume reduction of commercial transuranic wastes

International Nuclear Information System (INIS)

Oma, K.H.

1986-06-01

Pacific Northwest Laboratory (PNL) is evaluating alternatives and developing technology for treatment of radioactive wastes generated during commercial nuclear activities. Transuranic wastes that require volume reduction include spent HEPA filters, sample and analytical cell waste, and general process trash. A review of current technologies for volume reduction of these wastes led to the selection and testing of several low-speed shredder systems and three candidate incineration processes. The incinerators tested were the electrically heated control-led-air, gas-heated controlled-air, and rotary kiln. Equipment tests were conducted using simulated commercial transuranic wastes to provide a data base for the comparison of the various technologies. The electrically driven, low-speed shredder process was selected as the preferred method for size reduction of the wastes prior to incineration. All three incinerators effectively reduced the waste volume. Based on a technical and economic evaluation on the incineration processes, the recommended system for the commercial waste application is the gas-heated controlled-air incinerator with a single stage of shredding for feed pretreatment
Environmental and other evaluations of alternatives for management of defense transuranic waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1982-04-01

Appendices to this report contain the following information: INEL history of Waste Management; text of communications between Idaho and the federal government on long-term management; agency and public response to a proposed environmental impact statement; updated estimates on radiological releases from the slagging-pyrolysis incinerator; modeling studies of subsurface migration of radionuclides; nonradiological emissions and their environmental effects; methods for calculating radiological consequences; analysis of abnormal events in conceptual retrieval and processing operations; environmental contamination by accidental releases; hazards to waste management workers; environmental and other effects of rail and truck shipment of wastes; effects of hypothetical worst-case shipping accidents in urban areas; environmental and other effects of processing INEL transuranic waste at the offsite geological repository; and regulations applicable to INEL TRU waste management
Remote-handled transuranic system assessment appendices. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.
Remote-handled transuranic system assessment appendices. Volume 2

International Nuclear Information System (INIS)

1995-11-01

Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives
Transuranic-waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

McKinley, K.B.

1982-11-01

This report summarizes the objectives and accomplishments of Transuranic (TRU) Waste Program conducted at EG and G Idaho, Inc., during FY 1982. The TRU Waste Program included: (1) Preparation of a revised draft of the Recommendation of a Long-Term Strategy (RLTS) document; (2) Preparation of environmental documentation, including a technical report, Environmental and Other Evaluations of Alternatives for Management of Defense Transuranic Waste at the Idaho National Engineering Laboratory, IDO-10103, as well as two environmental evaluations; (3) Preparation of a certification plan and procedures; (4) A nondestructive examination (NDE) project, which includes development of real-time radiography for waste certification, and container integrity equipment for waste container certification; (5) Development of an assay system; (6) Completion of a conceptual design for the Stored Waste Examination Pilot Plant (SWEPP) and SWEPP Support; and (7) Gas-generation analyses and tests. These TRU waste projects were funded at $1640K
US experience with acid digestion of combustible transuranic wastes

International Nuclear Information System (INIS)

Allen, C.R.; Lerch, R.E.

1982-09-01

Contaminated transuranic waste from a plutonium finishing plant has been processed in a waste treatment demonstration plant, the Radioactive Acid Digestion Test Unit (RADTU) located at Hanford, Washington, USA. Waste treatment experience, including process and equipment performance, the behavior of plutonium in the system, and chemical and nuclear safety are all discussed. The complementary relationship of this research and development to that at the ALONA pilot plant in Mol, Belgium is noted. 7 figures, 4 tables
The implications of RCRA [Resource Conservation and Recovery Act] regulation for the disposal of transuranic and high-level waste

International Nuclear Information System (INIS)

Sigmon, C.F.; Sharples, F.E.; Smith, E.D.

1988-01-01

In May of 1987 the Department of Energy (DOE) published a rule interpreting the definition of ''byproduct'' under the Atomic Energy Act. This byproduct rule clarified the role of the Resource Conservation and Recovery Act (RCRA) in the regulation of DOE's radioactive waste management activities. According to the rule, only the radioactive portion of DOE's mixed radioactive and hazardous waste (mixed waste), including mixed transuranic (TRU) and high-level waste (HLW), is exempt from RCRA under the byproduct exemption. The portion of a waste that is hazardous as defined by RCRA is subject to full regulation under RCRA. Because the radioactive and hazardous portions of m any, if not most, DOE wastes are likely to be inseparable, the rule in effect makes most mixed wastes subject to dual regulation. The potential application of RCRA to facilities such as the Waste Isolation Pilot Plant (WIPP) and the HLW repository creates unique challenges for both the DOE and regulatory authorities. Strategies must be developed to assure compliance with RCRA without either causing excessive administrative burdens or abandoning the goal of minimizing radiation exposure. This paper will explore some of the potential regulatory options for and recent trends in the regulation of TRU and HLW under RCRA
Safety analysis and inventory control of transuranic and low-level waste in common storage

International Nuclear Information System (INIS)

Porten, D.R.; Bonner, A.L.; Joyce, J.P.

1993-01-01

This paper describes a methodology developed For the inventory control of low-level waste (LLW) and transuranic (TRU) waste, when both are stored in the same location, and both contribute to an inventory constrained by safety considerations. Development of the method arose from the necessity to make safety analysis calculations for the addition of LLW, in quantities greater than existing inventory limits would allow when stored with TRU waste, in the Hanford Central Waste Complex (CWC)-Ensuring that the dose consequences of credible releases are maintained at low-hazard limits or less, was used to allow greater than Type A quantities of LLW into the CWC. Basically, what happens is the original limited amount of TRU allowed is reduced by some equivalent amount of LLW introduced. The total quantity of TRU, and LLW in excess of Type A quantities, must be administratively maintained via curie equivalency Factors to ensure operation as a low-hazard Facility. The ''equivalency'' between TRU and LLW proposed here is specific only to the CWC, but the methodology can be used for other specific applications, such as TRU and LLW storage or handling facilities where inventory limits must be enforced or where a simplified inventory system is required
Assessment of change in shallow land burial limits for defense transuranic waste

International Nuclear Information System (INIS)

Cohen, J.J.; Smith, C.F.; Spaeth, M.E.; Ciminesi, F.J.; Dickman, P.T.; O'Neal, D.A.

1983-03-01

There is an emerging consensus within the waste management technical community that the current concentration limit of 10 nCi/g for shallow land burial (SLB) of transuranic (TRU) waste is excessively restrictive. A concentration limit for SLB in the range of 100 to 1000 nCi/g is reasonable and justifiable based upon these reasons: Resultant increase in collective radiation dose (total population dose) would be very small, and the net detriment to public health would be negligible. Increasing the limit is cost-effective and could save hundreds of millions of dollars for the national economy over time. The hazard resulting from the increased SLB limit for TRU would be significantly less than that due to many naturally occurring mineral deposits and/or human activities. Expenditures directed toward health and safety conform to the economic law of diminishing returns: as the absolute expenditure increases, the marginal return decreases. Excessive restriction of the TRU concentration limit for SLB needlessly diverts limited resources (time, talent, and money) from other areas of health and safety where they might be more beneficially applied. Despite considerable effort, this study did not find any compelling technical argument to maintain the limit for TRU in SLB at 10 nCi/g. Subsequent to the initial preparation of this document, the US Department of Energy issued DOE Order 5820 which raises the administrative disposal limit for transuranic wastes from 10 nCi/g to 100 nCi/g. In addition, the US Nuclear Regulatory Commission has subsequently proposed and adopted a revised version of regulation 10 CFR 61 in which the disposal limit for shallow land burial of Category C (intruder protected) waste is set at 100 nCi/g
Certification document for newly generated contact-handled transuranic waste

International Nuclear Information System (INIS)

Box, W.D.; Setaro, J.

1984-01-01

The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP
Transuranic waste characterization sampling and analysis methods manual. Revision 1

International Nuclear Information System (INIS)

Suermann, J.F.

1996-04-01

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits
Final waste management programmatic environmental impact statement for managing treatment, storage, and disposl of radioactive and hazardous waste. Volume II

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Volume II is an integral part of the Office of Environmental Management''s (EM''s) Waste Management Programmatic Environmental Impact Statement (WM PEIS), which portrays the impacts of EM''s waste management activities at each of the 17 major DOE sites evaluated in the WM PEIS

Transuranic elements in marine environments

International Nuclear Information System (INIS)

Bowen, V.T.

1975-04-01

Transuranic elements are present in marine environments as a result of worldwide fallout, close-in fallout, the SNAP-9A burnup, pipeline disposal of reprocessing wastes, neutron capture by uranium in one-pass cooling-water reactors and the B-52 crash in Thule, Greenland. Distributions and movements of 239 Pu, 240 Pu, 241 Am, and 137 Cs from these introductions in the Atlantic Ocean are being studied partly because the transuranic elements themselves are geochemically interesting, partly because they appear to serve as tracers for specific oceanographic processes, and partly because of concern that man is faced with the problem of disposal of rapidly increasing amounts of transuranics as radioactive waste, and that we must be able, soon, to predict the fates and the effects of those amounts that reach the coastal waters or the deep oceans. Plutonium and americium are widely distributed in the oceans as a result of man's activities. Both appear to be more mobile than expected, and Pu shows little behavior in these environments that had been predicted from laboratory studies. Although their associations with biological material seem to be most striking for rooted plants or Sargassum, it is too premature to dismiss the possibility of their being a real hazard to marine life
Case studies of corrosion of mixed waste and transuranic waste drums

International Nuclear Information System (INIS)

Kosiewicz, S.T.

1993-01-01

This paper presents three case studies of corrosion of waste drums at the Los Alamos National Laboratory (LANL). Corrosion was not anticipated by the waste generators, but occurred because of subtle chemical or physical mechanisms. In one case, drums of a cemented transuranic (TRU) sludge experienced general and pitting corrosion. In the second instance, a chemical from a commercial paint stripper migrated from its primary containment drums to chemically attack overpack drums made of mild carbon steel. In the third case, drums of mixed low level waste (MLLW) soil corroded drum packaging even though the waste appeared to be dry when it was placed in the drums. These case studies are jointly discussed as ''lessons learned'' to enhance awareness of subtle mechanisms that can contribute to the corrosion of radioactive waste drums during interim storage
Nuclear waste: Department of Energy's Transuranic Waste Disposal Plan needs revision

International Nuclear Information System (INIS)

1986-01-01

Transuranic waste consists of discarded tools, rags, machinery, paper, sheet metal, and glass containing man-made radioactive elements that can be dangerous if inhaled, ingested, or absorbed into the body through an open wound. GAO found that the Defense Waste Management Plan does not provide the Congress with complete inventory and cost data or details on environmental and safety issues related to the permanent disposal of TRU waste; the Plan's $2.8 billion costs are understated by at least $300 million. Further, it does not include costs for disposing of buried waste, contaminated soil, and TRU waste that may not be accepted at the Waste Isolation Pilot Plant. Lastly, the Plan provides no details on the environmental and safety issues related to the permanent disposal of TRU waste, nor does it discuss the types of or timing for environmental analyses needed before WIPP starts operating
Remote-handled transuranic waste study

International Nuclear Information System (INIS)

1995-10-01

The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation's defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs
In situ grouting of buried transuranic waste with polyacrylamide

International Nuclear Information System (INIS)

Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

1987-01-01

This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs
In situ grouting of buried transuranic waste with polyacrylamide

Energy Technology Data Exchange (ETDEWEB)

Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K.; Supaokit, P.

1987-01-01

This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs.
In situ grouting of buried transuranic waste

International Nuclear Information System (INIS)

Spalding, B.P.; Lee, S.Y.

1987-01-01

This task is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34,000 liters of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. The grout was also completely contained within the two trenches as no grout constituents were observed in the 12 perimeter ground water monitoring wells. Polyacrylamide grout was selected for field demonstration over polyacrylate grout because of its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty of controlling the set time of the acrylate polymerization process in the presence of potassium ferricyanide. Based on preliminary degradation monitoring, polyacrylamide was estimated to have a microbiological half-life of 115 years in the test soil. However, this calculated value is likely to be conservatively low because microbial degradation of the grout set accelerator or residual monomer may be contributing most to the measured microbial respiration. Addition work, using 14 C-labeled acrylate and acrylamide grouts, is being carried out to more accurately estimate the grouts' microbiological half-life
Assessment of LANL transuranic mixed waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from the evaluation of the Los Alamos National Laboratory (LANL) TRU Mixed Waste Acceptance Criteria to determine its compliance with applicable DOE requirements. The driving requirements for s TRU Mixed Waste Acceptance Criteria are essentially those contained in the ''TRU Waste Acceptance Criteria for the Waste Isolation Pilot Plant'' or WIPP WAC (DOE Report WIPP-DOE-069), 40 CFR 261-270, and DOE Order 5820.2A (Radioactive Waste Management), specifically Chapter II which is entitled ''Management of Transuranic Waste''. The primary purpose of the LANL WAC is the establishment of those criteria that must be met by generators of TRU mixed waste before such waste can be accepted by the Waste Management Group. An annotated outline of a genetic TRU mixed waste acceptance criteria document was prepared from those requirements contained in the WIPP WAC, 40 CFR 261-270, and 5820.2A, and is based solely upon those requirements
Supplement analysis of transuranic waste characterization and repackaging activities at the Idaho National Engineering Laboratory in support of the Waste Isolation Pilot Plant test program

International Nuclear Information System (INIS)

1991-03-01

This supplement analysis has been prepared to describe new information relevant to waste retrieval, handling, and characterization at the Idaho National Engineering Laboratory (INEL) and to evaluate the need for additional documentation to satisfy the National Environmental Policy Act (NEPA). The INEL proposes to characterize and repackage contact-handled transuranic waste to support the Waste Isolation Pilot Plant (WIPP) Test Phase. Waste retrieval, handling and processing activities in support of test phase activities at the WIPP were addressed in the Supplemental Environmental Impact Statement (SEIS) for the WIPP. To ensure that test-phase wastes are properly characterized and packaged, waste containers would be retrieved, nondestructively examined, and transported from the Radioactive Waste Management Complex (RWMC) to the Hot-Fuel Examination Facility for headspace gas analysis, visual inspections to verify content code, and waste acceptance criteria compliance, then repackaging into WIPP experimental test bins or returned to drums. Following repackaging the characterized wastes would be returned to the RWMC. Waste characterization would help DOE determine WIPP compliance with US Environmental Protection Agency regulations governing disposal of transuranic waste and hazardous waste. Additionally, this program supports onsite compliance with Resource Conservation and Recovery Act (RCRA) requirements, compliance with the terms of the No-Migration Variance at WIPP, and provides data to support future waste shipments to WIPP. This analysis will help DOE determine whether there have been substantial changes made to the proposed action at the INEL, or if preparation of a supplement to the WIPP Final Environmental Impact Statement (DOE, 1980) and SEIS (DOE, 1990a) is required. This analysis is based on current information and includes details not available to the SEIS
Filter testing and development for prolonged transuranic service and waste reduction

International Nuclear Information System (INIS)

Geer, J.A.; Buttedahl, O.I.; Skaats, C.D.; Terada, K.; Woodard, R.W.

1977-02-01

The life of High Efficiency Particulate Air (HEPA) filters used in transuranic service is influenced greatly by the gaseous and particulate matter to which the filters are exposed. The most severe conditions encountered at Rocky Flats are at the ventilation systems serving the plutonium recovery operations in Bldg. 771. A project of filter testing and development for prolonged transuranic service and waste reduction was formally initiated at Rocky Flats on July 1, 1975. The project is directed toward improving filtration methods which will prolong the life of HEPA filter systems without sacrificing effectiveness. Another important aspect of the project is to reduce the volume of HEPA filter waste shipped from the plant for long-term storage. Progress to September 30, 1976, is reported
Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

International Nuclear Information System (INIS)

Metzger, J.C.; Snyder, A.M.

1977-09-01

The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods
Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage

International Nuclear Information System (INIS)

1993-12-01

This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes
FY85 Program plan for the Defense Transuranic Waste Program (DTWP)

International Nuclear Information System (INIS)

1984-11-01

The Defense TRU Waste Program (DTWP) is the focal point for the Department of Energy in national planning, integration, and technical development for TRU waste management. The scope of this program extends from the point of TRU waste generation through delivery to a permanent repository. The TRU program maintains a close interface with repository development to ensure program compatibility and coordination. The defense TRU program does not directly address commercial activities that generate TRU waste. Instead, it is concerned with providing alternatives to manage existing and future defense TRU wastes. The FY85 Program Plan is consistent with the Defense TRU Waste Program goals and objectives stated in the Defense Transuranic Waste Program Strategy Document, January 1984. The roles of participants, the responsibilities and authorities for Research and Development (R and D), the organizational interfaces and communication channels for R and D and the establishment of procedures for planning, reporting, and budgeting of all R and D activities meet requirements stated in the Technical Management Plan for the Transuranic Waste Management Program. The Program Plan is revised as needed. The work breakdown structure is reflected graphically immediately following the Administration section and is described in the subsequent narrative. Detailed budget planning (i.e., programmatic funding and capital equipment) is presented for FY85; outyear budget projections are presented for future years
Critical evaluation of the limit of transuranic contamination of low level waste

International Nuclear Information System (INIS)

Rodger, W.A.

1976-01-01

The suggested limit for transuranics of 10 nanocuries/gram as a break point at which wastes should go to a national repository is seriously questioned. It is shown that insofar as protection of water supplies is concerned, the key to the problem is $sup 90$Sr, not transuranics, and in any case, the limit should be based on a site-determined inventory, not on concentration. Concentration is only important as a protection for future stumblers who might dig into the waste. Calculations are presented to show that for this purpose the limit should be higher by several orders of magnitude. The 10 nanocurie/gram should be used as a definition of complete innocuousness. 4 refs
Transuranic waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

Smith, T.H.; Tolman, C.R.

1980-12-01

This document summarizes the objectives and technical achievements of the transuranic (TRU) waste research and development program conducted at EG and G Idaho, Inc., during fiscal year 1980. The TRU waste activities covered in this report include: INEL TRU Waste EIS (Environmental Impact Statement), including preparation of the EIS, Support Studies, and the Public Participation Program; INEL TRU Waste Projects, including System Analysis, Stored Waste projects, and Buried Waste projects; and Waste Management Materials Studies, including Process Control and Durability studies
Westinghouse Hanford Company plan for certifying newly generated contact -- handled transuranic waste. Revision 1

International Nuclear Information System (INIS)

Lipinski, R.M.; Backlund, E.G.

1995-09-01

All transuranic (TRU) waste generators are required by US Department of Energy (DOE) Order 5820.2A to package their TRU waste in order to comply wit the Waste Isolation Pilot Plant (WIPP) -- Waste Acceptance Criteria (WAC) or keep non-certifiable containers segregated. The Westinghouse Hanford Company (WHC) Transuranic Waste Certification Plan was developed to ensure that TRU newly generated waste at WHC meets the DOE Order 5820.2A and the WHC-WAC which includes the State of Washington Department of Ecology -- Washington Administrative Code (DOE-WAC). The metho used at WHC to package TRU waste are described in sufficient detail to meet the regulations. This document is organized to provide a brief overview of waste generation operations at WHC. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. This plan describes how WHC complies with all applicable regulations and requirements set forth in the latest approved revision of WHC-EP-0063-4
The transuranic waste management program at Savannah River

International Nuclear Information System (INIS)

D'Ambrosia, J.

1986-01-01

Defense transuranic waste at the Savannah River site results from the Department of Energy's national defense activities, including the operation of production reactors, fuel reprocessing plants, and research and development activities. TRU waste has been retrievably stored at the Savannah River Plant since 1974 awaiting disposal. The Waste Isolation Pilot Plant, now under construction in New Mexico, is a research and development facility for demonstrating the safe disposal of defense TRU waste, including that in storage at the Savannah River Plant. The major objective of the TRU Program at SR is to support the TRU National Program, which is dedicated to preparing waste for, and emplacing waste in, the WIPP. Thus, the SR Program also supports WIPP operations. The SR site specific goals are to phase out the indefinite storage of TRU waste, which has been the mode of waste management since 1974, and to dispose of the defense TRU waste. This paper describes the specific activities at SR which will provide for the disposal of this TRU waste
Long-term management USDOE transuranic waste

International Nuclear Information System (INIS)

Bennett, W.S.; Gilbert, K.V.; Lowrey, R.Y.

1982-01-01

Activities for permanent disposal of US DOE TRU waste are presently focused on newly generated and stored waste. The buried waste and contaminated soils pose no near term problem. Decisions on any possible actions for these wastes will be deferred until the newly generated and stored wastes are being placed into disposal on a routine basis. Several elements must be in place before such disposal can become routine. These elements consist of: a disposal facility; waste acceptance criteria; waste certification mechanisms; waste processing facilities; and a waste transportation system. Each of these elements has been the subject of considerable activity in the recent past. Progress and plans for each element are summarized. As of January 1981, DOE has 60,500 m 3 of waste classified as Transuranic waste (TRU) in retrievable storage, and projects that additional TRU waste will be generated at an average rate of 4500 m 3 per year for the next 10 years. Over 99% of this waste is contact handled, with the remainder being remote handled, i.e., surface radiation dose levels exceeding 200 mrem/h. An estimated 273,000 m 3 of TRU waste were placed in shallow land burial prior to establishment of the 1970 policy. In addition, large quantities of soil at DOE sites are contaminated with TRU elements due to disposal of liquid wastes and by contact of soil with solid, buried waste whose original containers are now badly degraded. Possibly as much as 10,000,000 m 3 of soil are contaminated above 10 nCi/gm. Less than 1,000,000 m 3 are estimated to be contaminated above 100 nCi/gm
Radioactive waste management: a series of bibliographies. Transuranic wastes. Supplement 1

International Nuclear Information System (INIS)

McLaren, L.H.

1985-04-01

This bibliography contains information on transuranic waste included in the Department of Energy's Energy Data Base from August 1982 through December 1983. The abstracts are grouped by subject category as shown in the table of contents. Entries in the subject index also facilitate access by subject, e.g., Alpha-Bearing Wastes/Packaging. Within each category the arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number
Mediated electrochemical hazardous waste destruction

International Nuclear Information System (INIS)

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

1992-03-01

There are few permitted processes for mixed waste (radioactive plus chemically hazardous) treatment. We are developing an electrochemical process, based upon mediated electrochemical oxidation (MEO), that converts toxic organic components of mixed waste to water, carbon dioxide, and chloride or chloride precipitates. Aggressive oxidizer ions such as Ag 2+ , Co 3+ , or Fe 3+ are produced at an anode. These can attack organic molecules directly, and may also produce hydroxyl free radicals that promote destruction. Solid and liquid radioactive waste streams containing only inorganic radionuclide forms may be treated with existing technology and prepared for final disposal. The coulombic efficiency of the process has been determined, as well as the destruction efficiency for ethylene glycol, a surrogate waste. 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(II) has been used as a mediator in this process. Fe(III) and Co(III) are attractive alternatives to Ag(II) since they form soluble chlorides during the destruction of chlorinated solvents. Furthermore, silver itself is toxic heavy metal. Quantitative data have been obtained for the complete oxidation of ethylene glycol by Fe(III) and Co(III). Though ethylene glycol is a nonhalogenated organic, these data have enabled us to make direct comparisons of activities of Fe(III) and Co(III) with Ag(II). Very good quantitative data for the oxidation of ethylene glycol by Ag(II) had already been collected

Induction melting of simulated transuranic waste

International Nuclear Information System (INIS)

Tenaglia, R.D.; McCall, J.L.

1983-06-01

Coreless induction melting was investigated as a method to melt and consolidate waste material representative of the transuranic waste (TRU) stored at the Idaho National Engineering Laboratory (INEL). Waste material was introduced onto the surface of a molten cast iron bath in a coreless induction furnace. Waste metallics were incorporated into the bath. Noncombustibles formed a slag which was poured or skimmed from the bath surface. Stack sampling was performed to characterize the off-gas and particulate matter evolved. Experimental melting tests were performed for a variety of types of wastes including metallics, chemical sludge, soil, concrete, and glass. Each test also included a representative level of combustible materials consisting of paper, wood, cloth, polyvinyl chloride and polyethylene. Metallic wastes were readily processed by induction melting with a minimum of slag production. Test waste consisting primarily of chemical sludge provided fluid slags which could be poured from the bath surface. Processing of wastes consisting of soil, concrete, or glass was limited by the inability to achieve fluid slags. It appears from test results that coreless induction melting is a feasible method to process INEL-type waste materials if two problems can be resolved. First, slag fluidity must be improved to facilitate the collection of slags formed from soil, concrete, or glass containing wastes. Secondly, refractory life must be further optimized to permit prolonged processing of the waste materials. The use of a chrome-bearing high-alumina refractory was found to resist slag line attach much better than a magnesia refractory, although some attack was still noted
Gas generation from transuranic waste degradation: an interim assessment

International Nuclear Information System (INIS)

Molecke, M.A.

1979-10-01

A review of all available, applicable data pertaining to gas generation from the degradation of transuranic waste matrix material and packaging is presented. Waste forms are representative of existing defense-related TRU wastes and include cellulosics, plastics, rubbers, concrete, process sludges, and mild steel. Degradation mechanisms studied were radiolysis, thermal, bacterial, and chemical corrosion. Gas generation rates are presented in terms of moles of gas produced per year per drum, and in G(gas) values for radiolytic degradation. Comparison of generation rates is made, as is a discussion of potential short- and long-term concerns. Techniques for reducing gas generation rates are discussed. 6 figures, 10 tables
Remote-Handled Transuranic Waste Content Codes (RH-Trucon)

International Nuclear Information System (INIS)

2006-01-01

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC). The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: (1) A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. (2) A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is ''3''. The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR
76 FR 33277 - Proposed Approval of the Central Characterization Project's Remote-Handled Transuranic Waste...

Science.gov (United States)

2011-06-08

... disposal of TRU radioactive waste. As defined by the WIPP Land Withdrawal Act (LWA) of 1992 (Pub. L. 102... certification of the WIPP's compliance with disposal regulations for TRU radioactive waste [63 Federal Register... radioactive remote-handled (RH) transuranic (TRU) waste characterization program implemented by the Central...
An integrated systems approach to remote retrieval of buried transuranic waste using a telerobotic transport vehicle, innovative end effector, and remote excavator

International Nuclear Information System (INIS)

Smith, A.M.; Rice, P.; Hyde, R.; Peterson, R.

1995-02-01

Between 1952 and 1970, over two million cubic feet of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. Commingled with this two million cubic feet of waste is up to 10 million cubic feet of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate technologies for excavating, and transporting buried transuranic wastes at the INEL, and other hazardous or radioactive waste sites throughout the US Department of Energy complex. The full-scale demonstration, conduced at RAHCO Internationals facilities in Spokane, Washington, in the summer of 1994, evaluated equipment performance and techniques for digging, dumping, and transporting buried waste. Three technologies were evaluated in the demonstration: an Innovative End Effector for dust free dumping, a Telerobotic Transport Vehicle to convey retrieved waste from the digface, and a Remote Operated Excavator to deploy the Innovative End Effector and perform waste retrieval operations. Data were gathered and analyzed to evaluate retrieval performance parameters such as retrieval rates, transportation rates, human factors, and the equipment's capability to control contamination spread
Los Alamos Transuranic Waste Size Reduction Facility

International Nuclear Information System (INIS)

Harper, J.; Warren, J.

1987-06-01

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype. The facility is operated to remotely cut and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. We have found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes. 2 figs., 1 tab
Application of the iron-enriched basalt waste form for immobilizing commercial transuranic waste

International Nuclear Information System (INIS)

Owen, D.E.

1981-08-01

The principal sources of commercial transuranic (TRU) waste in the United States are identified. The physical and chemical nature of the wastes from these sources are discussed. The fabrication technique and properties of iron-enriched basalt, a rock-like waste form developed for immobilizing defense TRU wastes, are discussed. The application of iron-enriched basalt to commercial TRU wastes is discussed. Review of commercial TRU wastes from mixed-oxide fuel fabrication, light water reactor fuel reprocessing, and miscellaneous medical, research, and industrial sources, indicates that iron-enriched basalt is suitable for most types of commercial TRU wastes. Noncombustible TRU wastes are dissolved in the high temperature, oxidizing iron-enriched basalt melt. Combustible TRU wastes are immobilized in iron-enriched basalt by incinerating the wastes and adding the TRU-bearing ash to the melt. Casting and controlled cooling of the melt produces a devitrified, rock-like iron-enriched basalt monolith. Recommendations are given for testing the applicability of iron-enriched basalt to commercial TRU wastes
Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

International Nuclear Information System (INIS)

2003-01-01

This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS
Technologies for recovery of transuranics and immobilization of non-high-level wastes

International Nuclear Information System (INIS)

Richardson, G.L.

1976-06-01

This paper supplements the preceding Symposium paper on ''Treatment Technologies for Non-High-Level Wastes (U.S.A.)'' by C. R. Cooley and D. E. Clark (HEDL-SA-851), and covers the additional treatment technologies in use and under development for recovering transuranics and immobilizing non-high-level wastes for transportation and storage. Methods used for nondestructive assay (NDA) of TRU elements in non-high-level wastes are also discussed briefly
Immobilization of hazardous and radioactive waste into glass structures

International Nuclear Information System (INIS)

Wicks, G.G.

1997-01-01

As a result of more than three decades of international research, glass has emerged as the material of choice for immobilization of a wide range of potentially hazardous radioactive and non-radioactive materials. The ability of glass structures to incorporate and then immobilize many different elements into durable, high integrity, waste glass products is a direct function of the unique random network structure of the glassy state. Every major country involved with long-term management of high-level radioactive waste (HLW) has either selected or is considering glass as the matrix of choice for immobilizing and ultimately, disposing of the potentially hazardous, high-level radioactive material. There are many reasons why glass is preferred. Among the most important considerations are the ability of glass structures to accommodate and immobilize the many different types of radionuclides present in HLW, and to produce a product that not only has excellent technical properties, but also possesses good processing features. Good processability allows the glass to be fabricated with relative ease even under difficult remote-handling conditions necessary for vitrification of highly radioactive material. The single most important property of the waste glass produced is its ability to retain hazardous species within the glass structure and this is reflected by its excellent chemical durability and corrosion resistance to a wide range of environmental conditions. In addition to immobilization of HLW glass matrices are also being considered for isolation of many other types of hazardous materials, both radioactive as well as nonradioactive. This includes vitrification of various actinides resulting from clean-up operations and the legacy of the cold war, as well as possible immobilization of weapons grade plutonium resulting from disarmament activities. Other types of wastes being considered for immobilization into glasses include transuranic wastes, mixed wastes, contaminated
Controlled air incineration of hazardous chemical and mixed waste at Los Alamos

International Nuclear Information System (INIS)

Borduin, L.C.; Hutchins, D.A.; Vavruska, J.J.; Warner, C.L.

1987-01-01

The Los Alamos National Laboratory (LANL) Controlled Air Incineration (CAI) system, originally developed for transuranic (TRU) waste volume reduction studies, is currently being qualified for hazardous chemical and mixed waste treatment under provisions of the Resource Conservation and Recovery Act (RCRA). The objective is to obtain a permanent RCRA Part B permit for thermal disposal of hazardous and mixed wastes generated by LANL. Constructed in the mid-1970s as a demonstration project for incineration of TRU solid wastes, the CAI process was substantially modified and tested in 1980-1983 for acceptance of both liquid and solid hazardous chemicals. Successful demonstration of TRU solid waste processing objectives in 1979 and later chemical waste incineration studies have been documented in several publications. In 1984, the LANL CAI became the first US Dept. of Energy (DOE) incinerator to be permitted for polychlorinated biphenyl disposal under the Toxic Substances Control Act. Following establishment of Environmental Protection Agency (EPA) jurisdiction over DOE chemical waste management in 1984, LANL sought and was granted interim status for the CAI and applied for a trial burn permit in the overall laboratory RCRA Part B application. A trial burn and final report have been completed; results have been submitted to EPA and the New Mexico Environmental Improvement Division. This paper provides an overview of trial burn planning and results together with the operational status of LANL's CAI
Processing of transuranic waste at the Savannah River Plant

International Nuclear Information System (INIS)

Daugherty, B.A.; Gruber, L.M.; Mentrup, S.J.

1986-01-01

Transuranic wastes at the Savannah River Plant (SRP) have been retrievably stored on concrete pads since early 1972. This waste is stored primarily in 55-gallon drums and large carbon steel boxes. Higher activity drums are placed in concrete culverts. In support of a National Program to consolidate and permanently dispose of this waste, a major project is planned at SRP to retrieve and process this waste. This project, the TRU Waste Facility (TWF), will provide equipment and processes to retrieve TRU waste from 20-year retrievable storage and prepare it for permanent disposal at the Waste Isolation Pilot Plant (WIPP) geological repository in New Mexico. This project is an integral part of the SRP Long Range TRU Waste Management Program to reduce the amount of TRU waste stored at SRP. The TWF is designed to process 15,000 cubic feet of retrieved waste and 6200 cubic feet of newly generated waste each year of operation. This facility is designed to minimize direct personnel contact with the waste using state-of-the-art remotely operated equipment
Los Alamos Transuranic Waste Size Reduction Facility

International Nuclear Information System (INIS)

Harper, J.; Warren, J.

1987-01-01

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype completed in 1981 and later modified during 1986 to enhance production. The facility is operated to remotely cut (with a plasma arc torch) and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. It was found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes
Hazardous Waste

Science.gov (United States)

... chemicals can still harm human health and the environment. When you throw these substances away, they become hazardous waste. Some hazardous wastes come from products in our homes. Our garbage can include such hazardous wastes as old batteries, bug spray cans and paint thinner. U.S. residents ...
Full-scale retrieval of simulated buried transuranic waste

International Nuclear Information System (INIS)

Valentich, D.J.

1993-09-01

This report describes the results of a field test conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive) test pit (1,100 yd 3 volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, tanks, vaults, pipes, and beams, were also placed in the pit. These materials were intended to simulate the type of wastes found in TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were observed. The feasibility of teleoperating reading equipment was also addressed
Design considerations for incineration of transuranic-contaminated solid wastes

International Nuclear Information System (INIS)

Koenig, R.A.

1977-01-01

The Los Alamos Scientific Laboratory has established a development program to evaluate alternate production-level (100-200 lb/hr throughput) volume reduction processes for transuranic-contaminated solid waste. The first process selected for installation and study is based on controlled-air incineration. Design considerations leading to selection of feed preparation, incineration, residue removal, and off-gas cleanup components and their respective radioactive containment provisions will be presented
Preliminary assessment of nine waste-form products/processes for immobilizing transuranic wastes

International Nuclear Information System (INIS)

Crisler, L.R.

1980-09-01

Nine waste-form processes for reduction of the present and projected Transuranic (TRU) waste inventory to an immobilized product have been evaluated. Product formulations, selected properties, preparation methods, technology status, problem areas needing resolution and location of current research development being pursued in the United States are discussed for each process. No definitive utility ranking is attempted due to the early stage of product/process development for TRU waste containing products and the uncertainties in the state of current knowledge of TRU waste feed compositional and quantitative makeup. Of the nine waste form products/processes included in this discussion, bitumen and cements (encapsulation agents) demonstrate the degree of flexibility necessary to immobilize the wide composition range present in the TRU waste inventory. A demonstrated process called Slagging Pyrolysis Incineration converts a varied compositional feed (municipal wastes) to a ''basalt'' like product. This process/product appears to have potential for TRU waste immobilization. The remaining waste forms (borosilicate glass, high-silica glass, glass ceramics, ''SYNROC B'' and cermets) have potential for immobilizing a smaller fraction of the TRU waste inventory than the above discussed waste forms
Waste Management Facilities Cost Information for transportation of radioactive and hazardous materials. Revision 1

International Nuclear Information System (INIS)

Feizollahi, F.; Shropshire, D.; Burton, D.

1994-09-01

This report contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, greater-than-Class C (GTCC) LLW and DOE equivalent waste, transuranic waste (TRU), spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled ( 200 mrem/hr contact dose) radioactive waste have been estimated previously, and a summary has been included in earlier WMFCI reports. In order to have a single source for obtaining transportation cost for all radioactive waste, the transportation costs for the contact- and remote-handled wastes are repeated in this report. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the US Department of Transportation (DOT), the US Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations. It should be noted that the trend is toward greater restrictions on transportation of radioactive waste (e.g., truck or rail car speed, shipping route, security escort, and personnel training requirements), which may have a significant impact on future costs
Los Alamos Controlled Air Incinerator for hazardous chemical and mixed radioactive wastes

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Koenig, R.A.; Warner, C.L.

1986-01-01

The Los Alamos Controlled Air Incinerator (CAI) is currently the only radioactive waste incineration facility in the US permitted to treat polychlorinated biphenyls (PCBs). The CAI was developed in the mid-1970's as a demonstration system for volume reduction of transuranic (TRU) contaminated combustible solid wastes. It has since undergone additions and modifications to accommodate hazardous chemical wastes in response to a need within the Department of Energy (DOE) to treat mixed radioactive/chemical wastes. An overview of these additions which include a liquid feed system, a high intensity liquid injection burner, and an activated carbon adsorption unit is presented here. Also included is a discussion of the procedures required for Toxic Substances Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) permitting of the CAI
Project Strategy For The Remediation And Disposition Of Legacy Transuranic Waste At The Savannah River Site, South Carolina, USA

International Nuclear Information System (INIS)

Rodriguez, M.

2010-01-01

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

IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

International Nuclear Information System (INIS)

UYTIOCO EM

2007-01-01

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington
Evaluation of forms for the immobilization of high-level and transuranic wastes

International Nuclear Information System (INIS)

Schuman, R.P.; Cox, N.D.; Gibson, G.W.; Kelsey, P.V. Jr.

1982-08-01

A figure-of-merit (FOM) analysis has been made of a number of waste forms for solidifying both defense and commercial high-level reprocessing waste (HLW) and transuranic (TRU) wastes. The evaluation includes iron-enriched basalt (IEB), a fusion-produced glass-ceramic, which has not been included in other assessments. For HLW, concrete receives the highest FOM, but may not meet regulatory requirements; IEB and glass are the best choices of the materials that should easily meet regulatory requirements. Concrete waste forms are the best choice for TRU wastes, with IEB a close contender. 116 references, 3 figures, 112 tables
Westinghouse Hanford Company plan for certifying newly generated contact-handled transuranic waste for emplacement in the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Lipinski, R.M.; Sheehan, J.S.

1992-07-01

Westinghouse Hanford Company (Westinghouse Hanford) currently manages an interim storage site for Westinghouse Hanford and non-Westinghouse Hanford-generated transuranic (TRU) waste and operates TRU waste generating facilities within the Hanford Site in Washington State. Approval has been received from the Waste Acceptance Criteria Certification Committee (WACCC) and Westinghouse Hanford TRU waste generating facilities to certify newly generated contact-handled TRU (CH-TRU) solid waste to meet the Waste Acceptance Criteria (WAC). This document describes the plan for certifying newly generated CH-TRU solid waste to meet the WAC requirements for storage at the Waste Isolation Pilot Plant (WIPP) site. Attached to this document are facility-specific certification plans for the Westinghouse Hanford TRU waste generators that have received WACCC approval. The certification plans describe operations that generate CH-TRU solid waste and the specific procedures by which these wastes will be certified and segregated from uncertified wastes at the generating facilities. All newly generated CH-TRU solid waste is being transferred to the Transuranic Storage and Assay Facility (TRUSAF) and/or a controlled storage facility. These facilities will store the waste until the certified TRU waste can be sent to the WIPP site and the non-certified TRU waste can be sent to the Waste Receiving and Processing Facility. All non-certifiable TRU waste will be segregated and clearly identified
The effect of vibration on alpha radiolysis of transuranic (TRU) waste

International Nuclear Information System (INIS)

Zerwekh, A.; Kosiewicz, S.; Warren, J.

1993-01-01

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data
Preoperational checkout of the remote-handled transuranic waste handling at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1987-09-01

This plan describes the preoperational checkout for handling Remote-Handled Transuranic (RH-TRU) Wastes from their receipt at the Waste Isolation Pilot Plant (WIPP) to their emplacement underground. This plan identifies the handling operations to be performed, personnel groups responsible for executing these operations, and required equipment items. In addition, this plan describes the quality assurance that will be exercised throughout the checkout, and finally, it establishes criteria by which to measure the success of the checkout. 7 refs., 5 figs
Stored Transuranic Waste Management Program at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Clements, T.L.

1996-01-01

Since 1970, INEL has provided interim storage capacity for transuranic (TRU)-contaminated wastes generated by activities supporting US national defense needs. About 60% of the nation's current inventory of TRU-contaminated waste is stored at INEL, awaiting opening of the Waste Isolation Pilot Plant (WIPP), the designated federal repository. A number of activities are currently underway for enhancing current management capabilities, conducting projects that support local and national TRU management activities, and preparing for production-level waste retrieval, characterization, examination, certification, and shipment of untreated TRU waste to WIPP in April 1998. Implementation of treatment capability is planned in 2003 to achieve disposal of all stored TRU-contaminated waste by a target date of December 31, 2015, but no later than December 31, 2018
Handbook of hazardous waste management

International Nuclear Information System (INIS)

Metry, A.A.

1980-01-01

The contents of this work are arranged so as to give the reader a detailed understanding of the elements of hazardous waste management. Generalized management concepts are covered in Chapters 1 through 5 which are entitled: Introduction, Regulations Affecting Hazardous Waste Management, Comprehensive Hazardous Waste Management, Control of Hazardous Waste Transportation, and Emergency Hazardous Waste Management. Chapters 6 through 11 deal with treatment concepts and are entitled: General Considerations for Hazardous Waste Management Facilities, Physical Treatment of Hazardous Wastes, Chemical Treatment of Hazardous Wastes, Biological Treatment of Hazardous Wastes, Incineration of Hazardous Wastes, and Hazardous Waste Management of Selected Industries. Chapters 12 through 15 are devoted to ultimate disposal concepts and are entitled: Land Disposal Facilities, Ocean Dumping of Hazardous Wastes, Disposal of Extremely Hazardous Wastes, and Generalized Criteria for Hazardous Waste Management Facilities
U.S. Department of Energy Implementation of Chemical Evaluation Requirements for Transuranic Waste Disposal at the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Moon, Alison [USDOE Office of Environmental Management (EM), Washington, DC (United States); Barkley, Michelle [USDOE Office of Environmental Management (EM), Washington, DC (United States); Poppiti, James [USDOE Office of Environmental Management (EM), Washington, DC (United States)

2017-07-01

This report summarizes new controls designed to ensure that transuranic waste disposed at the Waste Isolation Pilot Plant (WIPP) does not contain incompatible chemicals. These new controls include a Chemical Compatibility Evaluation, an evaluation of oxidizing chemicals, and a waste container assessment to ensure that waste is safe for disposal. These controls are included in the Chapter 18 of the Documented Safety Analysis for WIPP (1).
U.S. Department of Energy Implementation of Chemical Evaluation Requirements for Transuranic Waste Disposal at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Moon, Alison; Barkley, Michelle; Poppiti, James

2017-01-01

This report summarizes new controls designed to ensure that transuranic waste disposed at the Waste Isolation Pilot Plant (WIPP) does not contain incompatible chemicals. These new controls include a Chemical Compatibility Evaluation, an evaluation of oxidizing chemicals, and a waste container assessment to ensure that waste is safe for disposal. These controls are included in the Chapter 18 of the Documented Safety Analysis for WIPP (1).
Physical Properties of Hanford Transuranic Waste

Energy Technology Data Exchange (ETDEWEB)

Berg, John C.

2010-03-25

The research described herein was undertaken to provide needed physical property descriptions of the Hanford transuranic tank sludges under conditions that might exist during retrieval, treatment, packaging and transportation for disposal. The work addressed the development of a fundamental understanding of the types of systems represented by these sludge suspensions through correlation of the macroscopic rheological properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of the work have advanced existing understanding of the sedimentation and aggregation properties of complex colloidal suspensions. Bench scale models were investigated with respect to their structural, colloidal and rheological properties that should be useful for the development and optimization of techniques to process the wastes at various DOE sites.
Proposed Changes to EPA's Transuranic Waste Characterization Approval Process

International Nuclear Information System (INIS)

Joglekar, R.D.; Feltcorn, E.M.; Ortiz, A.M.

2003-01-01

This paper describes the changes to the waste characterization (WC) approval process proposed in August 2002 by the U.S. Environmental Protection Agency (EPA or the Agency or we). EPA regulates the disposal of transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) repository in Carlsbad, New Mexico. EPA regulations require that waste generator/storage sites seek EPA approval of WC processes used to characterize TRU waste destined for disposal at WIPP. The regulations also require that EPA verify, through site inspections, characterization of each waste stream or group of waste streams proposed for disposal at the WIPP. As part of verification, the Agency inspects equipment, procedures, and interviews personnel to determine if the processes used by a site can adequately characterize the waste in order to meet the waste acceptance criteria for WIPP. The paper discusses EPA's mandate, current regulations, inspection experience, and proposed changes. We expect that th e proposed changes will provide equivalent or improved oversight. Also, they would give EPA greater flexibility in scheduling and conducting inspections, and should clarify the regulatory process of inspections for both Department of Energy (DOE) and the public
Strategic management of health risks posed by buried transuranic wastes

International Nuclear Information System (INIS)

Jump, R.A.

1994-01-01

A strategy is presented for reducing health risks at sites contaminated with buried transuranic (TRU) wastes by first taking measures to immobilize the contaminants until the second step, final action, becomes cost-effective and poses less risk to the remediation workers. The first step of this strategy does not preclude further action if it is warranted and is in harmony with environmental laws and regulations
Management of transuranic wastes throughout the world

International Nuclear Information System (INIS)

Lakey, L.T.; Christensen, H.; De Jonghe, P.; Frejaville, G.; Lavie, J.M.; Thackrah, D.G.

1983-01-01

Transuranic (TRU) wastes are those radioactive wastes, except spent fuel and high-level wastes, that are contaminated with sufficient long-lived, alpha-emitting nuclides that the decay to innocuous levels in engineered storage structures or shallow-land burial sites cannot be used as a disposal method. This class of waste is produced principally during spent fuel reprocessing, recycle fuel fabrication, and weapons material production. At least ten countries are involved in operations producing this class of waste, which represents a small fraction of the alpha-emitting nuclides in the world's inventory and of the total volume of radioactive wastes produced in nuclear activities. No consensus has been reached on a numerical definition; definitions in use vary from >0.03 to >1000 nCi transuranium radionuclides per gram of waste (TRU/g). The definitions are presently used to separate wastes going to sea dumping or shallow-land burial from those requiring greater isolation. All countries emphasize plutonium recovery and volume reduction in their plans for treating TRU wastes. Incineration is the most prevalent treatment in use. When fixation is used, cement and bitumen are the preferred fixation media. All high-concentration TRU wastes are now being placed in interim storage. No TRU wastes are presently being disposed except the low-concentration wastes being dumped at sea by Belgium and the United Kingdom and those being injected into geologic strata by the United States (Oak Ridge National Laboratory) and the USSR. All countries prefer and are planning to use deep geologic repositories for final disposal of TRU wastes. According to present schedules, the Waste Isolation Pilot Plant (WIPP) facility in the United States, with a scheduled startup date of 1989, will be the first operating repository since the closure of the Federal Republic of Germany's Asse Salt Mine in 1977
Mediated electrochemical hazardous waste destruction

International Nuclear Information System (INIS)

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

1991-08-01

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 2+ or Ce +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
Transporting transuranic waste to the Waste Isolation Pilot Plant: Risk and cost perspectives

International Nuclear Information System (INIS)

Biwer, B. M.; Gilette, J. L.; Poch, L. A.; Suermann, J. F.

1999-01-01

The Waste Isolation Pilot Plant (WIPP) is an authorized US Department of Energy (DOE) research and development facility constructed near the city of Carlsbad in southeastern New Mexico. The facility is intended to demonstrate the safe disposal of transuranic (TRU) radioactive waste resulting from US defense activities. Under the WIPP Land Withdrawal Act of 1992 (LWA), federal lands surrounding the WIPP facility were withdrawn from all public use and the title of those lands was transferred to the Secretary of Energy. The DOE's TRU waste is stored, and in some cases is still being generated, at 10 large-quantity and 13 small-quantity sites across the US. After applicable certification requirements have been met, the TRU waste at these sites will be sent to the WIPP to initiate the disposal phase of the facility, which according to current planning is projected to last for approximately 35 years
The effects of transuranic separation on waste disposal

International Nuclear Information System (INIS)

1991-04-01

Rogers and Associates Engineering has analyzed waste streams from fuel cycles involving actinide partitioning and transmutation to determine appropriate disposal facilities for the waste and the cost of disposal. The focus of the study is the economic impact of actinide partitioning and transmutation on waste disposal, although there is a qualitative discussion of the impacts of actinide burning on disposal risk. This effort is part of a multi-contractor task being coordinated by the Electric Power Research Institute to address the technical feasibility and economic impact of transuranic burning. Waste streams were defined by General Electric Corporation for eight alternative processing cases -- involving aqueous and pyrochemical processing of spent fuel from light water reactors and liquid metal reactors and for low-actinide-recovery and high-actinide-recovery technologies. Disposal options are determined for three possible futures: one involving the present socio-political-licensing environment and using cost estimates for existing or planned facilities, an optimistic future with lower siting and licensing costs, and a pessimistic future with high siting and licensing costs and some extraordinary measures to assure waste isolation. The optimistic future allows the disposal of certain types of waste in a facility that provides a degree of waste isolation that is intermediate between a repository and a low-level-waste facility. 30 refs., 18 figs., 45 tabs
Scientific, institutional, regulatory, political, and public acceptance of the waste isolation pilot plant transuranic waste repository

International Nuclear Information System (INIS)

Eriksson, L.G.

2000-01-01

The recent successful certification and opening of a first-of-a-kind, deep geological repository for safe disposal of long-lived, transuranic radioactive waste (TRUW) at the Waste Isolation Pilot Plant (WIPP) site, New Mexico, United States of America (USA), embody both long-standing local and wide-spread, gradually achieved, scientific, institutional, regulatory, political, and public acceptance. The related historical background and development are outlined and the main contributors to the successful siting, certification, and acceptance of the WIPP TRUW repository, which may also serve as a model to success for other radioactive waste disposal programs, are described. (author)
Waste Isolation Pilot Plant remote-handled transuranic waste disposal strategy

International Nuclear Information System (INIS)

1995-01-01

The remote-handled transuranic (RH-TRU) waste disposal strategy described in this report identifies the process for ensuring that cost-effective initial disposal of RH-TRU waste will begin in Fiscal Year 2002. The strategy also provides a long-term approach for ensuring the efficient and sustained disposal of RH-TRU waste during the operating life of WIPP. Because Oak Ridge National Laboratory stores about 85 percent of the current inventory, the strategy is to assess the effectiveness of modifying their facilities to package waste, rather than constructing new facilities. In addition, the strategy involves identification of ways to prepare waste at other sites to supplement waste from Oak Ridge National Laboratory. DOE will also evaluate alternative packagings, modes of transportation, and waste emplacement configurations, and will select preferred alternatives to ensure initial disposal as scheduled. The long-term strategy provides a systemwide planning approach that will allow sustained disposal of RH-TRU waste during the operating life of WIPP. The DOE's approach is to consider the three relevant systems -- the waste management system at the generator/storage sites, the transportation system, and the WIPP disposal system -- and to evaluate the system components individually and in aggregate against criteria for improving system performance. To ensure full implementation, in Fiscal Years 1996 and 1997 DOE will: (1) decide whether existing facilities at Oak Ridge National Laboratory or new facilities to package and certify waste are necessary; (2) select the optimal packaging and mode of transportation for initial disposal; and (3) select an optimal disposal configuration to ensure that the allowable limits of RH-TRU waste can be disposed. These decisions will be used to identify funding requirements for the three relevant systems and schedules for implementation to ensure that the goal of initial disposal is met
Identification of potential transuranic waste tanks at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Colburn, R.P.

1995-05-05

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.
Identification of potential transuranic waste tanks at the Hanford Site

International Nuclear Information System (INIS)

Colburn, R.P.

1995-01-01

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document

Progress and Lessons Learned in Transuranic Waste Disposition at The Department of Energy's Advanced Mixed Waste Treatment Project

International Nuclear Information System (INIS)

J.D. Mousseau; S.C. Raish; F.M. Russo

2006-01-01

This paper provides an overview of the Department of Energy's (DOE) Advanced Mixed Waste Treatment Project (AMWTP) located at the Idaho National Laboratory (INL) and operated by Bechtel BWXT Idaho, LLC(BBWI) It describes the results to date in meeting the 6,000-cubic-meter Idaho Settlement Agreement milestone that was due December 31, 2005. The paper further describes lessons that have been learned from the project in the area of transuranic (TRU) waste processing and waste certification. Information contained within this paper would be beneficial to others who manage TRU waste for disposal at the Waste Isolation Pilot Plant (WIPP)
76 FR 4823 - Hazardous Waste Management System; Identifying and Listing Hazardous Waste Exclusion

Science.gov (United States)

2011-01-27

... Waste Management System; Identifying and Listing Hazardous Waste Exclusion AGENCY: Environmental... hazardous wastes. The Agency has decided to grant the petition based on an evaluation of waste-specific... excludes the petitioned waste from the requirements of hazardous waste regulations under the Resource...
Allowable residual contamination levels: transuranic advanced disposal systems for defense waste

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.

1982-01-01

An evaluation of advanced disposal systems for defense transuranic (TRU) wastes is being conducted using the Allowable Residual Contamination Level (ARCL) method. The ARCL method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. For defense TRU wastes at the Hanford Site near Richland, Washington, various advanced disposal techniques are being studied to determine their potential for application. This paper presents a discussion of the results of the first stage of the TRU advanced disposal systems project
Waste Generator Instructions: Key to Successful Implementation of the US DOE's 435.1 for Transuranic Waste Packaging Instructions (LA-UR-12-24155) - 13218

International Nuclear Information System (INIS)

French, David M.; Hayes, Timothy A.; Pope, Howard L.; Enriquez, Alejandro E.; Carson, Peter H.

2013-01-01

In times of continuing fiscal constraints, a management and operation tool that is straightforward to implement, works as advertised, and virtually ensures compliant waste packaging should be carefully considered and employed wherever practicable. In the near future, the Department of Energy (DOE) will issue the first major update to DOE Order 435.1, Radioactive Waste Management. This update will contain a requirement for sites that do not have a Waste Isolation Pilot Plant (WIPP) waste certification program to use two newly developed technical standards: Contact-Handled Defense Transuranic Waste Packaging Instructions and Remote-Handled Defense Transuranic Waste Packaging Instructions. The technical standards are being developed from the DOE O 435.1 Notice, Contact-Handled and Remote-Handled Transuranic Waste Packaging, approved August 2011. The packaging instructions will provide detailed information and instruction for packaging almost every conceivable type of transuranic (TRU) waste for disposal at WIPP. While providing specificity, the packaging instructions leave to each site's own discretion the actual mechanics of how those Instructions will be functionally implemented at the floor level. While the Technical Standards are designed to provide precise information for compliant packaging, the density of the information in the packaging instructions necessitates a type of Rosetta Stone that translates the requirements into concise, clear, easy to use and operationally practical recipes that are waste stream and facility specific for use by both first line management and hands-on operations personnel. The Waste Generator Instructions provide the operator with step-by-step instructions that will integrate the sites' various operational requirements (e.g., health and safety limits, radiological limits or dose limits) and result in a WIPP certifiable waste and package that can be transported to and emplaced at WIPP. These little known but widely productive Waste
Disposal of hazardous wastes

International Nuclear Information System (INIS)

Barnhart, B.J.

1978-01-01

The Fifth Life Sciences Symposium entitled Hazardous Solid Wastes and Their Disposal on October 12 through 14, 1977 was summarized. The topic was the passage of the National Resources Conservation and Recovery Act of 1976 will force some type of action on all hazardous solid wastes. Some major points covered were: the formulation of a definition of a hazardous solid waste, assessment of long-term risk, list of specific materials or general criteria to specify the wastes of concern, Bioethics, sources of hazardous waste, industrial and agricultural wastes, coal wastes, radioactive wastes, and disposal of wastes
West Valley Demonstration Project low-level and transuranic waste assay and methodology

International Nuclear Information System (INIS)

McVay, C.W.

1987-03-01

In the decontamination and decommissioning of the West Valley Nuclear Facility, waste materials are being removed and packaged in a variety of waste containers which require classification in accordance with USNRC 10 CFR 61 and DOE 5820.2 criteria. Low-Level and Transuranic waste assay systems have been developed to efficiently assay and classify the waste packages. The waste is assayed by segmented gamma scanning, passive neutron techniques, dose rate conversion, and/or radiochemical laboratory analysis. The systems are capable of handling all the waste forms currently packaged as part of the Project. The above systems produce a list of nuclides present with their concentrations and determines the classification of the waste packages based on criteria outlined in DOE Order 5820.2 and USNRC 10 CFR 61.55. 9 refs., 12 figs., 8 tabs
Vitrification of transuranic and beta-gamma contaminated solid wastes

International Nuclear Information System (INIS)

Dukes, M.D.

1980-06-01

Vitrification of solid transuranic contaminated (TRU) wastes alone and with high-level liquid wastes (HLLW) was studied. Homogeneous glasses containing 20 to 30 wt % ash were made by using glass frits previously developed at the Savannah River Plant and Pacific Northwest Laboratories. If the ash is vitrified along with the HLLW, 1.0 wt % as can be added to the waste forms without affecting their quality. This loading of ash is well above the loading required by the relative amounts of HLLW and TRU ash that will be processed at the Savannah River Plant. Vitrification of TRU-contaminated electropolishing sludges and high efficiency particular air filter materials along with HLLW would require an increase in the quantity of glass to be produced. However, if these TRU-contaminated solids were vitrified with the HLLW, the addition of low-level beta-gamma contaminated ash would require no further increase in glass production
Description of processes for the immobilization of selected transuranic wastes

International Nuclear Information System (INIS)

Timmerman, C.L.

1980-12-01

Processed sludge and incinerator-ash wastes contaminated with transuranic (TRU) elements may require immobilization to prevent the release of these elements to the environment. As part of the TRU Waste Immobilization Program sponsored by the Department of Energy (DOE), the Pacific Northwest Laboratory is developing applicable waste-form and processing technology that may meet this need. This report defines and describes processes that are capable of immobilizing a selected TRU waste-stream consisting of a blend of three parts process sludge and one part incinerator ash. These selected waste streams are based on the compositions and generation rates of the waste processing and incineration facility at the Rocky Flats Plant. The specific waste forms that could be produced by the described processes include: in-can melted borosilicate-glass monolith; joule-heated melter borosilicate-glass monolith or marble; joule-heated melter aluminosilicate-glass monolith or marble; joule-heated melter basaltic-glass monolith or marble; joule-heated melter glass-ceramic monolith; cast-cement monolith; pressed-cement pellet; and cold-pressed sintered-ceramic pellet
Mobile/Modular Deployment Project-Enhancing Efficiencies within the National Transuranic Waste Program

International Nuclear Information System (INIS)

Triay, I.R.; Basabilvazo, G.B.; Countiss, S.; Moody, D.C.; Behrens, R.G.; Lott, S.A.

2002-01-01

In 1999, the National Transuranic (TRU) Waste Program (NTP) achieved two significant milestones. First, the Waste Isolation Plant (WIPP) opened in March for the permanent disposal of TRU waste generated by, and temporarily stored at, various sites supporting the nation's defense programs. Second, the Hazardous Waste Facility Permit, issued by the New Mexico Environment Department, for WIPP became effective in November. While the opening of WIPP brought to closure a number of scientific, engineering, regulatory, and political challenges, achieving this major milestone led to a new set of challenges-how to achieve the Department of Energy's (DOE's) NTP end-state vision: All TRU waste from DOE sites scheduled for closure is removed All legacy TRU waste from DOE sites with an ongoing nuclear mission is disposed 0 All newly generated TRU waste is disposed as it is generated The goal is to operate the national TRU waste program safely, cost effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. The existing schedule for TRU waste disposition would achieve the NTP vision in 2034 at an estimated life-cycle cost of $16B. The DOE's Carlsbad Field Office (CBFO) seeks to achieve this vision early-by at least 10 years- while saving the nation an estimated $48 to $6B. CBFO's approach is to optimize, or to make as functional as possible, TRU waste disposition. That is, to remove barriers that impede waste disposition, and increase the rate and cost efficiency of waste disposal at WIPP, while maintaining safety. The Mobile/Modular Deployment Project (MMDP) is the principal vehicle for implementing DOE's new commercial model of using best business practices of national authorization basis, standardization, and economies of scale to accelerate the completion of WIPP's mission. The MMDP is one of the cornerstones of the National TRU Waste System Optimization Project (1). The objective of the MMDP is to increase TRU
DOE Hazardous Waste Program

International Nuclear Information System (INIS)

Eyman, L.D.; Craig, R.B.

1985-01-01

The goal of the DOE Hazardous Waste Program is to support the implementation and improvement of hazardous-chemical and mixed-radioactive-waste management such that public health, safety, and the environment are protected and DOE missions are effectively accomplished. The strategy for accomplishing this goal is to define the character and magnitude of hazardous wastes emanating from DOE facilities, determine what DOE resources are available to address these problems, define the regulatory and operational constraints, and develop programs and plans to resolve hazardous waste issues. Over the longer term the program will support the adaptation and application of technologies to meet hazardous waste management needs and to implement an integrated, DOE-wide hazardous waste management strategy. 1 reference, 1 figure
Research and development plans for disposal of high-level and transuranic wastes

International Nuclear Information System (INIS)

Bartlett, J.W.; Platt, A.M.

1978-09-01

This plan recommends a 20-year, 206 million (1975 $'s) R and D program on geologic structures in the contiguous U.S. and on the midplate Pacific seabed with the objective of developing an acceptable method for disposal of commercial high-level and transuranic wastes by 1997. No differentiation between high-level and transuranic waste disposal is made in the first 5 years of the program. A unique application of probability theory to R and D planning establishes, at a 95% confidence level, that the program objective will be met if at least fifteen generic options and five specific disposal sites are explored in detail and at least two pilot plants are constructed and operated. A parallel effort on analysis and evaluation maximizes information available for decisions on the acceptability of the disposal techniques. Based on considerations of technical feasibility, timing and technical risk, the other disposal concepts, e.g., ice sheets, partitioning, transmutation and space disposal cited in BNWL-1900 are not recommended for near future R and D
Density, movement, and transuranic tissue inventory of small mammals at a liquid-radioactive waste disposal area

International Nuclear Information System (INIS)

Halford, D.K.

1987-01-01

Linear movement, density, and transuranic radionuclide inventory were estimated for small mammals residing at a liquid radioactive waste disposal area in southeastern Idaho. Deer mice (Peromyscus maniculatus), kangaroo rats (Dipodomys ordii), western harvest mice (Reithrodontomys megalotis), and Great Basin pocket mice (Perognathus parvus) were the predominant species. The total small mammal population within the 3.0-ha waste area was estimated to be 93. The distance between consecutive captures for all species combined averaged 41 m and ranged from 7 to 201 m. About 30% of the rodents captured inside the waste area were also captured outside its boundaries. The total population inventory of 238 Pu, /sup 239,240/Pu, 241 Am, 242 Cm, and 244 Cm was 44 pCi, 30 pCi, 19 pCi, 21 pCi, and <1 pCi, respectively. One-third, or about 35 pCi of transuranics, could be removed from the waste area by small mammals during the summer of 1981. 16 references, 3 figures, 3 tables
Report of the remote-handled transuranic waste mock retrieval demonstration

International Nuclear Information System (INIS)

1987-05-01

This report documents the results of the mock, onsite retrieval demonstration that was conducted on May 19 and 20, 1987, for representatives of the New Mexico Environmental Evaluation Group (EEG). Demonstration of the retrievability of remote-handled transuranic (RH TRU) waste is part of a milestone included in the Agreement for Consultation and Cooperation between the state of New Mexico and the United States Department of Energy. Retrieval equipment design documents and a retrievability demonstration plan for RH TRU waste were previously transmitted to the EEG. This report documents the results of the demonstration by evaluating the demonstration against the acceptance criteria that were established in the Demonstration Plan. 1 fig., 2 tabs
Research and development program for transuranic-contaminated waste within the U.S. Energy Research and Development Administration

International Nuclear Information System (INIS)

Wolfe, R.A.

1976-01-01

This overview examines the research and development program that has been established within the U.S. Energy Research and Development Administration (ERDA) to develop the technology to treat transuranic-contaminated waste. Also considered is the waste expected within the total nuclear fuel cycle
Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel and Transuranic Radioactive Wastes (40 CFR Part 191)

Science.gov (United States)

This regulation sets environmental standards for public protection from the management and disposal of spent nuclear fuel, high-level wastes and wastes that contain elements with atomic numbers higher than uranium (transuranic wastes).
Evaluation of extractant-coated magnetic microparticles for the recovery of hazardous metals from waste solution

International Nuclear Information System (INIS)

Kaminski, M. D.

1998-01-01

A magnetically assisted chemical separation (MACS) process was developed earlier at Argonne National Laboratory (ANL). This compact process was designed for the separation of transuranics (TRU) and radionuclides from the liquid waste streams that exist at many DOE sites, with an overall reduction in waste volume requiring disposal. The MACS process combines the selectivity afforded by solvent extractant/ion exchange materials with magnetic separation to provide an efficient chemical separation. Recently, the MACS process has been evaluated with acidic organophosphorus extractants for hazardous metal recovery from waste solutions. Moreover, process scale-up design issues have been addressed with respect to particle filtration and recovery. Two acidic organophosphorus compounds have been investigated for hazardous metal recovery, bis(2,4,4-trimethylpentyl) phosphinic acid (Cyanexreg-sign 272) and bis(2,4,4-trimethylpentyl) dithiophosphinic acid (Cyanexreg-sign 301). Coated onto magnetic microparticles, these extractants demonstrated superior recovery of hazardous metals from solution, relative to what was expected on the basis of results from solvent extraction experiments. The results illustrate the diverse applications of MACS technology for dilute waste streams. Preliminary process scale-up experiments with a high-gradient magnetic separator at Oak Ridge National Laboratory have revealed that very low microparticle loss rates are possible
Project plans for transuranic waste at small quantity sites in the Department of Energy comples-10522

International Nuclear Information System (INIS)

Mctaggart, Jerri Lynne; Lott, Sheila; Gadbury, Casey

2009-01-01

Los Alamos National Laboratory, Carlsbad Office (LANL-CO), has been tasked to write Project Plans for all of the Small Quantity Sites (SQS) with defense related Transuranic (TRU) waste in the Department of Energy (DOE) complex. Transuranic Work-Off Plans were precursors to the Project Plans. LANL-CO prepared a Work-Off Plan for each small quantity site. The Work-Off Plan that identified issues, drivers, schedules, and inventory. Eight sites have been chosen to deinventory their legacy TRU waste; Bettis Atomic Power Laboratory, General Electric-Vallecitos Nuclear Center, Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory-Area 300, Nevada Test Site, Nuclear Radiation Development, Sandia National Laboratory, and the Separations Process Research Unit. Each plan was written for contact and/or remote handled waste if present at the site. These project plans will assist the small quantity sites to ship legacy TRU waste offsite and de-inventory the site of legacy TRU waste. The DOE is working very diligently to reduce the nuclear foot print in the United States. Each of the eight SQSs will be de-inventoried of legacy TRU waste during a campaign that ends September 2011. The small quantity sites have a fraction of the waste that large quantity sites possess. During this campaign, the small quantity sites will package all of the legacy TRU waste and ship to Idaho or directly to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The sites will then be removed from the Transuranic Waste Inventory if they are de-inventoried of all waste. Each Project Plan includes the respective site inventory report, schedules, resources, drivers and any issues. These project plans have been written by the difficult waste team and will be approved by each site. Team members have been assigned to each site to write site specific project plans. Once the project plans have been written, the difficult team members will visit the sites to ensure nothing has
Savannah River Certification Plan for newly generated, contact-handled transuranic waste

International Nuclear Information System (INIS)

Wierzbicki, K.S.

1986-01-01

This Certification Plan document describes the necessary processes and methods for certifying unclassified, newly generated, contact-handled solid transuranic (TRU) waste at the Savannah River Plant and Laboratory (SRP, SRL) to comply with the Waste Isolation Pilot Plant Waste Acceptance Criteria (WIPP-WAC). Section 2 contains the organizational structure as related to waste certification including a summary of functional responsibilities, levels of authority, and lines of communication of the various organizations involved in certification activities. Section 3 describes general plant operations and TRU waste generation. Included is a description of the TRU Waste classification system. Section 4 contains the SR site TRU Waste Quality Assurance Program Plan. Section 5 describes waste container procurement, inspection, and certification prior to being loaded with TRU waste. Certification of waste packages, after package closure in the waste generating areas, is described in Section 6. The packaging and certification of individual waste forms is described in Attachments 1-5. Included in each attachment is a description of controls used to ensure that waste packages meet all applicable waste form compliance requirements for shipment to the WIPP. 3 figs., 3 tabs
The possible transmutation of radioactive waste from nuclear reactors

International Nuclear Information System (INIS)

Harries, J.R.

1974-01-01

A nuclear reactor power program produces high level and long lived radioactive wastes. The high level activity is associated with fission products, but beyond 400 years the principal waste hazard is from transuranic elements produced in the reactor. Several schemes have been proposed for the transmutation of the problem isotopes into more easily handled isotopes. The neutron flux in a thermal reactor is not high enough to significantly reduce the longer lived fission product isotopes 90 Sr and 132 Gs, but the transuranic elements can be reduced by recycling through power reactors. The limitation on recycling of the transuranic elements is the separation process to remove trace quantities from the waste stream. In fast reactors the transuranic elements are the principal fuel and fast reactor waste contains only half as much 90 Sr as thermal reactors. However, the overall waste hazard is similar to thermal reactors. A sufficiently intense neutron flux for fission product transmutation could perhaps be produced by a spallation reactor driven by a proton linear accelerator or a controlled thermonuclear reactor. However, both concepts are still some years in the future. Transmutation by accelerator sources of protons, electrons of gammas tend to require more energy than neutron transmutation. (author)
Radioactive mixed waste disposal

International Nuclear Information System (INIS)

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

A brief analysis and description of transuranic wastes in the subsurface disposal area of the radioactive waste management complex at INEL

International Nuclear Information System (INIS)

Arrenholz, D.A.; Knight, J.L.

1991-02-01

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area during the period 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and special-case wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and makes recommendations for future efforts at waste characterization. 20 refs., 3 figs., 17 tabs
Waste Generator Instructions: Key to Successful Implementation of the US DOE's 435.1 for Transuranic Waste Packaging Instructions (LA-UR-12-24155) - 13218

Energy Technology Data Exchange (ETDEWEB)

French, David M. [LANL EES-12, Carlsbad, NM, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Hayes, Timothy A. [LANL EES-12, Carlsbad, NM, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Pope, Howard L. [Aspen Resources Ltd., Inc., P.O. Box 3038, Boulder, CO 80307 (United States); Enriquez, Alejandro E. [LANL NCO-4, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Carson, Peter H. [LANL NPI-7, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)

2013-07-01

In times of continuing fiscal constraints, a management and operation tool that is straightforward to implement, works as advertised, and virtually ensures compliant waste packaging should be carefully considered and employed wherever practicable. In the near future, the Department of Energy (DOE) will issue the first major update to DOE Order 435.1, Radioactive Waste Management. This update will contain a requirement for sites that do not have a Waste Isolation Pilot Plant (WIPP) waste certification program to use two newly developed technical standards: Contact-Handled Defense Transuranic Waste Packaging Instructions and Remote-Handled Defense Transuranic Waste Packaging Instructions. The technical standards are being developed from the DOE O 435.1 Notice, Contact-Handled and Remote-Handled Transuranic Waste Packaging, approved August 2011. The packaging instructions will provide detailed information and instruction for packaging almost every conceivable type of transuranic (TRU) waste for disposal at WIPP. While providing specificity, the packaging instructions leave to each site's own discretion the actual mechanics of how those Instructions will be functionally implemented at the floor level. While the Technical Standards are designed to provide precise information for compliant packaging, the density of the information in the packaging instructions necessitates a type of Rosetta Stone that translates the requirements into concise, clear, easy to use and operationally practical recipes that are waste stream and facility specific for use by both first line management and hands-on operations personnel. The Waste Generator Instructions provide the operator with step-by-step instructions that will integrate the sites' various operational requirements (e.g., health and safety limits, radiological limits or dose limits) and result in a WIPP certifiable waste and package that can be transported to and emplaced at WIPP. These little known but widely
The waste isolation pilot plant transuranic waste repository: A case study in radioactive waste disposal safety and risk

Energy Technology Data Exchange (ETDEWEB)

Eriksson, Leif G. [GRAM, Inc., Albuquerque, NM (United States)

1999-12-01

The Waste Isolation Pilot Plant (WIPP) deep geological defense-generated transuranic radioactive waste (TRUW) repository in the United States was certified on the 13 of May 1998 and opened on the 26 of March 1999. Two sets of safety/performance assessment calculations supporting the certification of the WIPP TRUW repository show that the maximum annual individual committed effective dose will be 32 times lower than the regulatory limit and that the cumulative amount of radionuclide releases will be at least 10 times, more likely at least 20 times, lower than the regulatory limits. Yet, perceptions remain among the public that the WIPP TRUW repository imposes an unacceptable risk.
The waste isolation pilot plant transuranic waste repository: A case study in radioactive waste disposal safety and risk

International Nuclear Information System (INIS)

Eriksson, Leif G.

1999-01-01

The Waste Isolation Pilot Plant (WIPP) deep geological defense-generated transuranic radioactive waste (TRUW) repository in the United States was certified on the 13 of May 1998 and opened on the 26 of March 1999. Two sets of safety/performance assessment calculations supporting the certification of the WIPP TRUW repository show that the maximum annual individual committed effective dose will be 32 times lower than the regulatory limit and that the cumulative amount of radionuclide releases will be at least 10 times, more likely at least 20 times, lower than the regulatory limits. Yet, perceptions remain among the public that the WIPP TRUW repository imposes an unacceptable risk
Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

International Nuclear Information System (INIS)

DEROSA, D.C.

2000-01-01

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping
Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

DEROSA, D.C.

2000-01-13

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.
Roadmap for disposal of Electrorefiner Salt as Transuranic Waste.

Energy Technology Data Exchange (ETDEWEB)

Rechard, Robert P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Trone, Janis R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kalinina, Elena Arkadievna [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sanchez, Lawrence C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-12-01

The experimental breeder reactor (EBR-II) used fuel with a layer of sodium surrounding the uranium-zirconium fuel to improve heat transfer. Disposing of EBR-II fuel in a geologic repository without treatment is not prudent because of the potentially energetic reaction of the sodium with water. In 2000, the US Department of Energy (DOE) decided to treat the sodium-bonded fuel with an electrorefiner (ER), which produces metallic uranium product, a metallic waste, mostly from the cladding, and the salt waste in the ER, which contains most of the actinides and fission products. Two waste forms were proposed for disposal in a mined repository; the metallic waste, which was to be cast into ingots, and the ER salt waste, which was to be further treated to produce a ceramic waste form. However, alternative disposal pathways for metallic and salt waste streams may reduce the complexity. For example, performance assessments show that geologic repositories can easily accommodate the ER salt waste without treating it to form a ceramic waste form. Because EBR-II was used for atomic energy defense activities, the treated waste likely meets the definition of transuranic waste. Hence, disposal at the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, may be feasible. This report reviews the direct disposal pathway for ER salt waste and describes eleven tasks necessary for implementing disposal at WIPP, provided space is available, DOE decides to use this alternative disposal pathway in an updated environmental impact statement, and the State of New Mexico grants permission.
Progress and Lessons Learned in Transuranic Waste Disposition at The Department of Energy's Advanced Mixed Waste Treatment Project

Energy Technology Data Exchange (ETDEWEB)

J.D. Mousseau; S.C. Raish; F.M. Russo

2006-05-18

This paper provides an overview of the Department of Energy's (DOE) Advanced Mixed Waste Treatment Project (AMWTP) located at the Idaho National Laboratory (INL) and operated by Bechtel BWXT Idaho, LLC(BBWI) It describes the results to date in meeting the 6,000-cubic-meter Idaho Settlement Agreement milestone that was due December 31, 2005. The paper further describes lessons that have been learned from the project in the area of transuranic (TRU) waste processing and waste certification. Information contained within this paper would be beneficial to others who manage TRU waste for disposal at the Waste Isolation Pilot Plant (WIPP).
A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

International Nuclear Information System (INIS)

Arrenholz, D.A.; Knight, J.L.

1991-08-01

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs
A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

Energy Technology Data Exchange (ETDEWEB)

Arrenholz, D.A.; Knight, J.L.

1991-08-01

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs.
In situ vitrification - A potential remedial action technique for hazardous wastes

International Nuclear Information System (INIS)

Fitzpatrick, V.F.; Buelt, J.L.; Oma, K.H.; Timmerman, C.L.

1984-01-01

In situ vitrification (ISV) is an innovative technology being developed as a potential method for stabilizing transuranic (TRU) contaminated wastes in place. Although the process is being developed for TRU contaminated wastes, it is envisioned that the process could also be applied to hazardous chemical wastes. In situ vitrification (ISV) is the conversion of contaminated soil into a durable glass and crystalline wastes form through melting by joule heating. The technology for in situ vitrification is based upon electric melter technology developed at the Pacific Northwest Laboratory (PNL) for the immobilization of high-level nuclear waste. In situ vitrification was initially tested by researchers at PNL in August, 1980 (U.S. Patent 4,376,598). Since then, ISV has grown from a concept to an emerging technology through a series of 21 engineering-scale (laboratory) tests and 7 pilot-scale (field) tests. A large-scale system is currently being fabricated for testing. The program has been sponsored by the U.S. Department of Energy's (DOE) Richland Operations Office for potential application to Hanford TRU contaminated soil sites. A more detailed description outlining the power system design and the off-gas treatment system follows
Test phase plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US Department of Energy (DOE) has prepared this Test Phase Plan for the Waste Isolation Pilot Plant to satisfy the requirements of Public Law 102-579, the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act (LWA). The Act provides seven months after its enactment for the DOE to submit this Plan to the Environmental Protection Agency (EPA) for review. A potential geologic repository for transuranic wastes, including transuranic mixed wastes, generated in national-defense activities, the WIPP is being constructed in southeastern New Mexico. Because these wastes remain radioactive and chemically hazardous for a very long time, the WIPP must provide safe disposal for thousands of years. The DOE is developing the facility in phases. Surface facilities for receiving waste have been built and considerable underground excavations (2150 feet below the surface) that are appropriate for in-situ testing, have been completed. Additional excavations will be completed when they are required for waste disposal. The next step is to conduct a test phase. The purpose of the test phase is to develop pertinent information and assess whether the disposal of transuranic waste and transuranic mixed waste in the planned WIPP repository can be conducted in compliance with the environmental standards for disposal and with the Solid Waste Disposal Act (SWDA) (as amended by RCRA, 42 USC. 6901 et. seq.). The test phase includes laboratory experiments and underground tests using contact-handled transuranic waste. Waste-related tests at WIPP will be limited to contact-handled transuranic and simulated wastes since the LWA prohibits the transport to or emplacement of remote-handled transuranic waste at WIPP during the test phase
A passive-active neutron device for assaying remote-handled transuranic waste

International Nuclear Information System (INIS)

Estep, R.J.; Coop, K.L.; Deane, T.M.; Lujan, J.E.

1990-01-01

A combined passive-active neutron assay device was constructed for assaying remote-handled transuranic waste. A study of matrix and source position effects in active assays showed that a knowledge of the source position alone is not sufficient to correct for position-related errors in highly moderating or absorbing matrices. An alternate function for the active assay of solid fuel pellets was derived, although the efficacy of this approach remains to be established
Transuranic (Tru) waste volume reduction operations at a plutonium facility

Energy Technology Data Exchange (ETDEWEB)

Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

2010-01-01

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos
Transuranic (Tru) waste volume reduction operations at a plutonium facility

International Nuclear Information System (INIS)

Cournoyer, Michael E.; Nixon, Archie E.; Dodge, Robert L.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.

2010-01-01

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National
Transuranic (TRU) waste volume reduction operations at a plutonium facility

International Nuclear Information System (INIS)

Cournoyer, Michael E.; Nixon, Archie E.; Fife, Keith W.; Sandoval, Arnold M.; Garcia, Vincent E.; Dodge, Robert L.

2011-01-01

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actinide Processing Group at TA-55 uses one-meter or longer glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glovebox as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste volume generation by almost 2½ times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos
Incinerator development program for processing transuranic waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hedahl, T.G.

1982-01-01

In the fall of 1981, two short-term tests were conducted on a controlled air and a rotary kiln incinerator to assess their potential for processing transuranic (TRU) contaminated waste at the Idaho National Engineering Laboratory (INEL). The primary purpose of the test program was a proof-of-principle verification that the incinerators could achieve near-complete combustion of the combustible portion of the waste, while mixed with high percentages of noncombustible and metal waste materials. Other important test objectives were to obtain system design information including off-gas and end-product characteristics and incinerator operating parameters. Approximately 7200 kg of simulated (non-TRU) waste from the INEL were processed during the two tests
Hazardous Waste Manifest System

Science.gov (United States)

EPA’s hazardous waste manifest system is designed to track hazardous waste from the time it leaves the generator facility where it was produced, until it reaches the off-site waste management facility that will store, treat, or dispose of the waste.
Evaluation of alternatives for a second-generation transportation system for Department of Energy transuranic waste

International Nuclear Information System (INIS)

1984-01-01

Department of Energy (DOE) waste storage sites will ship their contact-handled (CH) and remote-handled (RH) transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) beginning FY 1989. The CH-TRU waste will be shipped in the Transuranic Package Transported (TRUPACT-I), a new packaging being developed by Sandia National Laboratories, Albuquerque/Transportation Technology Center. Some of the DOE TRU waste, however, might be unsuitable for shipment in TRUPACT-I, and is designated special-shipped (SS) TRU waste. The purposes of this study were to: (1) identify the quantity and characteristics of SS-TRU waste stored and generated at DOE facilities; (2) identify alternatives for managing the SS-TRU waste; and (3) make overall recommendations for managing the SS-TRU waste. Data on quantity and characteristics were gathered through coordinating visits to the sites and extracting information from each site's records. Representatives of DOE organizations and contractors set objectives for managing the SS-TRU waste. Alternative shipping systems were then identified for CH SS-TRU waste and RH SS-TRU waste. Evaluations of these alternatives considered how well they would satisfy each objective, and associated potential problems. The study recommends delaying the decision on how best to transport the CH SS-TRU waste to WIPP until the amount of SS-TRU processed waste in heavy drums is known. These conditions and choices are presented: a relatively small number of processed, heavy drums could be shipped most economically via TRUPACT-I, mixed with lighter drums of unprocessed waste. If a large number of heavy drums is to be shipped, a shorter and narrower version of TRUPACT-I would be preferred alternative. The Defense High-Level Waste cask is the recommended alternative system for shipping RH SS-TRU waste. 12 references, 15 figures, 22 tables
W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

Energy Technology Data Exchange (ETDEWEB)

Leist, K.J.

1998-02-18

The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report

International Nuclear Information System (INIS)

Leist, K.J.

1998-01-01

The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ''Compliant''and One Trip Port DO-07402B is designated as ''Non Compliant''. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it's state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation
1995 solid waste 30-year characteristics volume summary

International Nuclear Information System (INIS)

Templeton, K.J.; DeForest, T.J.; Rice, G.I.; Valero, O.J.

1995-10-01

The Hanford Site has been designated by the US Department of Energy (DOE) to store, treat, and dispose of solid waste received from both onsite and offsite generators. This waste is currently or planned to be generated from ongoing operations, maintenance and deactivation activities, decontamination and decommissioning (D ampersand D) of facilities, and environmental restoration (ER) activities. This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), describes the characteristics of the waste to be shipped to Hanford's SWOC. The physical waste forms and hazardous constituents are described for the low-level mixed waste (LLMW) and the transuranic - transuranic mixed waste (TWunderscoreTRUM)
MANAGEING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS

International Nuclear Information System (INIS)

WOJTASEK, R.D.; GREENWELL, R.D.

2005-01-01

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO 2 ), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective roll in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics
Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

International Nuclear Information System (INIS)

Jacobson, Victor Levon

2002-01-01

U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodium-bearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements
75 FR 58346 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste

Science.gov (United States)

2010-09-24

... Waste Management System; Identification and Listing of Hazardous Waste AGENCY: Environmental Protection... Chemical Company-Texas Operations (Eastman) to exclude (or delist) certain solid wastes generated by its Longview, Texas, facility from the lists of hazardous wastes. EPA used the Delisting Risk Assessment...
Project B-589, 300 Area transuranic waste interim storage project engineering study

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1985-08-01

The purpose of the study was to look at various alternatives of taking newly generated, remote-handled transuranic waste (caisson waste) in the 300 Area, performing necessary transloading operations and preparing the waste for storage. The prepared waste would then be retrieved when the Waste Isolation Pilot Plant becomes operational and transshipped to the repository in New Mexico with a minimum of inspection and packaging. The scope of this study consisted of evaluating options for the transloading of the TRU wastes for shipment to a 200 Area storage site. Preconceptual design information furnished as part of the engineering study is listed below: produce a design for a clean, sealed waste canister; hot cell loadout system for the waste; in-cell loading or handling equipment; determine transshipment cask options; determine assay system requirements (optional); design or specify transport equipment required; provide a SARP cost estimate; determine operator training requirements; determine waste compaction equipment needs if desirable; develop a cost estimate and approximate schedule for a workable system option; and update the results presented in WHC Document TC-2025
76 FR 55846 - Hazardous Waste Management System: Identification and Listing of Hazardous Waste: Carbon Dioxide...

Science.gov (United States)

2011-09-09

... carbon dioxide (CO 2 ) streams that are hazardous from the definition of hazardous waste, provided these... management under the Resource Conservation and Recovery Act (RCRA) to conditionally exclude carbon dioxide... 2050-AG60 Hazardous Waste Management System: Identification and Listing of Hazardous Waste: Carbon...
A Title 40 Code of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site - 8210

International Nuclear Information System (INIS)

G J Shott; V Yucel; L Desotell

2008-01-01

In 1986, 21 m 3 of transuranic (TRU) waste was inadvertently buried in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site (NTS). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is considered five options for management of the buried TRU waste. One option is to leave the waste in-place if the disposal can meet the requirements of Title 40 Code of Federal Regulations (CFR) Part 191, 'Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes'. This paper describes analyses that assess the likelihood that TRU waste in shallow land burial can meet the 40 CFR 191 standards for a geologic repository. The simulated probability of the cumulative release exceeding 1 and 10 times the 40 CFR 191.13 containment requirements is estimated to be 0.009 and less than 0.0001, respectively. The cumulative release is most sensitive to the number of groundwater withdrawal wells drilled through the disposal trench. The mean total effective dose equivalent for a member of the public is estimated to reach a maximum of 0.014 milliSievert (mSv) at 10,000 years, or approximately 10 percent of the 0.15 mSv 40 CFR 191.15 individual protection requirement. The dose is predominantly from inhalation of short-lived Rn-222 progeny in air produced by low-level waste disposed in the same trench. The transuranic radionuclide released in greatest amounts, Pu-239, contributes only 0.4 percent of the dose. The member of public dose is most sensitive to the U-234 inventory and the radon emanation coefficient. Reasonable assurance of compliance with the Subpart C groundwater protection standard is provided by site characterization data and hydrologic processes modeling which support a conclusion of no groundwater pathway within 10,000 years. Limited quantities of transuranic waste in a shallow land burial trench at the NTS can meet
75 FR 73972 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Removal of...

Science.gov (United States)

2010-11-30

... Waste Management System; Identification and Listing of Hazardous Waste; Removal of Direct Final.... Lists of Subjects in 40 CFR Part 261 Environmental Protection, Hazardous waste, Recycling, Reporting and... follows: PART 261--IDENTIFICATION AND LISTING OF HAZARDOUS WASTE 0 1. The authority citation for part 261...
Waste management and chemical inventories

Energy Technology Data Exchange (ETDEWEB)

Gleckler, B.P.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the classification and handling of waste at the Hanford Site. Waste produced at the Hanford Site is classified as either radioactive, nonradioactive, or mixed waste. Radioactive wastes are further categorized as transuranic, high-level, and low-level. Mixed waste may contain both radioactive and hazardous nonradioactive substances. This section describes waste management practices and chemical inventories at the site.
Waste management and chemical inventories

International Nuclear Information System (INIS)

Gleckler, B.P.

1995-01-01

This section of the 1994 Hanford Site Environmental Report summarizes the classification and handling of waste at the Hanford Site. Waste produced at the Hanford Site is classified as either radioactive, nonradioactive, or mixed waste. Radioactive wastes are further categorized as transuranic, high-level, and low-level. Mixed waste may contain both radioactive and hazardous nonradioactive substances. This section describes waste management practices and chemical inventories at the site
Uncertainty analysis of a nondestructive radioassay system for transuranic waste

International Nuclear Information System (INIS)

Harker, Y.D.; Blackwood, L.G.; Meachum, T.R.; Yoon, W.Y.

1996-01-01

Radioassay of transuranic waste in 207 liter drums currently stored at the Idaho National Engineering Laboratory is achieved using a Passive Active Neutron (PAN) nondestructive assay system. In order to meet data quality assurance requirements for shipping and eventual permanent storage of these drums at the Waste Isolation Pilot Plant in Carlsbad, New Mexico, the total uncertainty of the PAN system measurements must be assessed. In particular, the uncertainty calculations are required to include the effects of variations in waste matrix parameters and related variables on the final measurement results. Because of the complexities involved in introducing waste matrix parameter effects into the uncertainty calculations, standard methods of analysis (e.g., experimentation followed by propagation of errors) could not be implemented. Instead, a modified statistical sampling and verification approach was developed. In this modified approach the total performance of the PAN system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. This paper describes the simulation process and illustrates its application to waste comprised of weapons grade plutonium-contaminated graphite molds
Incineration method for volume reduction and disposal of transuranic waste

International Nuclear Information System (INIS)

Borham, B.M.

1985-01-01

The Process Experimental Pilot Plant (PREPP) at Idaho National Engineering Laboratory (INEL) is designed to process 7 TPD of transuranic (TRU) waste producing 8.5 TPD of cemented waste and 4100 ACFM of combustion gases with a volume reduction of up to 17:1. The waste and its container are shredded then fed to a rotary kiln heated to 1700 0 F, then cooled and classified by a trommel screen. The fine portion is mixed with a cement grout which is placed with the coarse portion in steel drums for disposal at the Waste Isolation Pilot Plant (WIPP). The kiln off-gas is reheated to 2000 0 F to destroy any remaining hydrocarbons and toxic volatiles. The gases are cooled and passed in a venturi scrubber to remove particulates and corrosive gases. The venturi off-gas is passed through a mist eliminator and is reheated to 50 0 F above the dew point prior to passing through a High Efficiency Particulate Air (HEPA) filter. The scrub solution is concentrated to 25% solids by an inertial filter. The sludge containing the combustion chemical contaminants is encapsulated with the residue of the incinerated waste
Planning a transportation system for US Defense Transuranic waste

International Nuclear Information System (INIS)

Gilbert, K.V.; Hurley, J.D.; Smith, L.J.; McFadden, M.H.; Raudenbush, M.H.; Fedie, M.L.

1983-05-01

The development and planning of a transportation system for US Department of Energy (USDOE) Defense Transuranic (TRU) waste has required the talents and expertise of many people. Coordination activities, design activities, fabrication, research and development, operations, and transportation are but a few of the areas around which this system is built. Due to the large number of organizations, regulations and personalities the planning task becomes extremely complex. The intent of this paper is to discuss the steps taken in planning this system, to identify the various organizations around which this system is designed, and to discuss program progress to date, scheduling, and future plans. 9 figures, 1 table
Planning a transportation system for US defense transuranic waste

International Nuclear Information System (INIS)

Gilbert, K.V.; Hurley, J.D.; Smith, L.J.; McFadden, M.H.; Raudenbush, M.H.; Fedie, M.L.

1983-01-01

The development and planning of a transportation system for US Department of Energy (USDOE) Defense Transuranic (TRU) waste has required the talents and expertise of many people. Coordination activities, design activities, fabrication, research and development, operations, and transportation are but a few of the areas around which this system is built. Due to the large number of organizations, regulations and personalities the planning task becomes extremely complex. The intent of this paper is to discuss the steps taken in planning this system, to identify the various organizations around which this system is designed, and to discuss program progress to date, scheduling, and future plans
Physical Properties of Hanford Transuranic Waste. Final Report

International Nuclear Information System (INIS)

Berg, John C.

2010-01-01

The research described herein was undertaken to provide needed physical property descriptions of the Hanford transuranic tank sludges under conditions that might exist during retrieval, treatment, packaging and transportation for disposal. The work addressed the development of a fundamental understanding of the types of systems represented by these sludge suspensions through correlation of the macroscopic rheological properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of the work have advanced existing understanding of the sedimentation and aggregation properties of complex colloidal suspensions. Bench scale models were investigated with respect to their structural, colloidal and rheological properties that should be useful for the development and optimization of techniques to process the wastes at various DOE sites.
TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

International Nuclear Information System (INIS)

1989-01-01

Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig
Status of microwave process development for RH-TRU [remote-handled transuranic] wastes at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

White, T.L.; Youngblood, E.L.; Berry, J.B.; Mattus, A.J.

1990-01-01

The Oak Ridge National Laboratory (ORNL) Waste Handling and Packaging Plant is developing a microwave process to reduce and solidify remote-handled transuranic (RH-TRU) liquids and sludges presently stored in large tanks at ORNL. Testing has recently begun on an in-drum microwave process using nonradioactive RH-TRU surrogates. The microwave process development effort has focused on an in-drum process to dry the RH-TRU liquids and sludges in the final storage container and then melt the salt residues to form a solid monolith. A 1/3-scale proprietary microwave applicator was designed, fabricated, and tested to demonstrate the essential features of the microwave design and to provide input into the design of the full-scale applicator. The microwave fields are uniform in one dimension to reduce the formation of hot spots on the microwaved wasteform. The final wasteform meets the waste acceptance criteria for the Waste Isolation Pilot Plant, a federal repository for defense transuranic wastes near Carlsbad, New Mexico. 7 refs., 1 fig., 1 tab
75 FR 57686 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste Amendment

Science.gov (United States)

2010-09-22

... Waste Management System; Identification and Listing of Hazardous Waste Amendment AGENCY: Environmental...) 260.20 and 260.22 allows facilities to demonstrate that a specific waste from a particular generating facility should not be regulated as a hazardous waste. Based on waste-specific information provided by the...
Properties of vitrified rocky flats TRUW with different waste loadings

International Nuclear Information System (INIS)

Eddy, T.L.; Sears, J.W.; Grandy, J.D.; Miley, D.V.; Erickson, A.W.; Farnsworth, R.N.; Larsen, E.D.

1994-01-01

Leach rates, phase structures, and mechanical properties of simulated Rocky Flats Plant 1st and 2nd slate sludge vitrified in an arc melter are described as a function of waste to soil fraction and method of devitrification to produce the glass-ceramic waste form. Volatile, hazardous, and transuranic (TRU) surrogate metals were added to assess dissolution effects. Zirconia and titania were also added to confirm their ability as transuranic-surrogate getters

76 FR 16534 - Hazardous Waste Management System Identification and Listing of Hazardous Waste; Final Exclusion

Science.gov (United States)

2011-03-24

... Waste Management System Identification and Listing of Hazardous Waste; Final Exclusion AGENCY...) on a one-time basis from the lists of hazardous waste, a certain solid waste generated at its Mt... waste is [[Page 16535
Hazardous industrial waste management

International Nuclear Information System (INIS)

Quesada, Hilda; Salas, Juan Carlos; Romero, Luis Guillermo

2007-01-01

The appropriate managing of hazardous wastes is a problem little dealed in the wastes management in the country. A search of available information was made about the generation and handling to internal and external level of the hazardous wastes by national industries. It was worked with eleven companies of different types of industrial activities for, by means of a questionnaire, interviews and visits, to determine the degree of integral and suitable handling of the wastes that they generate. It was concluded that exist only some isolated reports on the generation of hazardous industrial wastes and handling. The total quantity of wastes generated in the country was impossible to establish. The companies consulted were deficient in all stages of the handling of their wastes: generation, accumulation and storage, transport, treatment and final disposition. The lack of knowledge of the legislation and of the appropriate managing of the wastes is showed as the principal cause of the poor management of the residues. The lack of state or private entities entrusted to give services of storage, transport, treatment and final disposition of hazardous wastes in the country was evident. (author) [es
Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

International Nuclear Information System (INIS)

Martell, M.A.; Hansen, F.; Weiner, R.

1998-01-01

Use of nature's laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia
Hazardous waste management in research laboratories

International Nuclear Information System (INIS)

Sundstrom, G.

1989-01-01

Hazardous waste management in research laboratories benefits from a fundamentally different approach to the hazardous waste determination from industry's. This paper introduces new, statue-based criteria for identifying hazardous wastes (such as radiological mixed wastes and waste oils) and links them to a forward-looking compliance of laboratories, the overall system integrates hazardous waste management activities with other environmental and hazard communication initiatives. It is generalizable to other waste generators, including industry. Although only the waste identification and classification aspects of the system are outlined in detail here, four other components are defined or supported, namely: routine and contingency practices; waste treatment/disposal option definition and selection; waste minimization, recycling, reuse, and substitution opportunities; and key interfaces with other systems, including pollution prevention
Limits for the burial of the Department of Energy transuranic wastes

Energy Technology Data Exchange (ETDEWEB)

Healy, J.W.; Rodgers, J.C.

1979-01-15

Potential limits for the shallow earth burial of transuranic elements were examined by simplified models of the individual pathways to man. Pathways examined included transport to surface steams, transport to ground water, intrusion, and people living on the burial ground area after the wastes have surfaced. Limits are derived for each pathway and operational limits are suggested based upon a dose to the organ receiving the maximum dose rate of 0.5 rem/y after 70 years of exposure for the maximum exposed individual.
Limits for the burial of the Department of Energy transuranic wastes

International Nuclear Information System (INIS)

Healy, J.W.; Rodgers, J.C.

1979-01-01

Potential limits for the shallow earth burial of transuranic elements were examined by simplified models of the individual pathways to man. Pathways examined included transport to surface steams, transport to ground water, intrusion, and people living on the burial ground area after the wastes have surfaced. Limits are derived for each pathway and operational limits are suggested based upon a dose to the organ receiving the maximum dose rate of 0.5 rem/y after 70 years of exposure for the maximum exposed individual
Transuranic waste examination quality assurance at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bower, J.M.

1987-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). A major objective of the Department of Energy (DOE) Nuclear Waste Management Programs is the proper management of the defense-generated TRU waste. The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored contact handled TRU waste in order to certify it to the Waste Isolation Pilot Plant Waste Acceptance Crtieria (WIPP-WAC). SWEPP's capabilities for certifying contact handled waste containers include weighing, real-time radiographic examination, fissile material assay examination, container integrity examination, radiological surveys and labeling of waste containers. These processes involve not only instrument accuracy but also a wide range of technician interpretation from moderate on the assay to 100% on the radiograph. This, therefore, requires a variety of quality assurance techniques to ensure that the examinations and certifications are being performed correctly. The purpose of this paper is to discuss the methods utilized by SWEPP for checking on the examination process and to ensure that waste certifications are being properly performed. Included is the application of the quality assurance techniques to each examination system, the management of the data generated by the examination, and the verifications to ensure accurate certification. 1 ref
Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 3. Appendices M-V

International Nuclear Information System (INIS)

1986-03-01

The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)
Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 2. Appendices A-L

International Nuclear Information System (INIS)

1986-03-01

The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)
Transuranic (TRU) Waste Repackaging at the Nevada Test Site

International Nuclear Information System (INIS)

Di Sanza, E.F.; Pyles, G.; Ciucci, J.; Arnold, P.

2009-01-01

This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada Test Site's (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M and O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum
Nuclear waste and hazardous waste in the public perception

International Nuclear Information System (INIS)

Kruetli, Pius; Seidl, Roman; Stauffacher, Michael

2015-01-01

The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.
Nuclear waste and hazardous waste in the public perception

Energy Technology Data Exchange (ETDEWEB)

Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

2015-07-01

The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.
Defense Remote Handled Transuranic Waste Cost/Schedule Optimization Study

International Nuclear Information System (INIS)

Pierce, G.D.; Wolaver, R.W.; Carson, P.H.

1986-11-01

The purpose of this study is to provide the DOE information with which it can establish the most efficient program for the long management and disposal, in the Waste Isolation Pilot Plant (WIPP), of remote handled (RH) transuranic (TRU) waste. To fulfill this purpose, a comprehensive review of waste characteristics, existing and projected waste inventories, processing and transportation options, and WIPP requirements was made. Cost differences between waste management alternatives were analyzed and compared to an established baseline. The result of this study is an information package that DOE can use as the basis for policy decisions. As part of this study, a comprehensive list of alternatives for each element of the baseline was developed and reviewed with the sites. The principle conclusions of the study follow. A single processing facility for RH TRU waste is both necessary and sufficient. The RH TRU processing facility should be located at Oak Ridge National Laboratory (ORNL). Shielding of RH TRU to contact handled levels is not an economic alternative in general, but is an acceptable alternative for specific waste streams. Compaction is only cost effective at the ORNL processing facility, with a possible exception at Hanford for small compaction of paint cans of newly generated glovebox waste. It is more cost effective to ship certified waste to WIPP in 55-gal drums than in canisters, assuming a suitable drum cask becomes available. Some waste forms cannot be packaged in drums, a canister/shielded cask capability is also required. To achieve the desired disposal rate, the ORNL processing facility must be operational by 1996. Implementing the conclusions of this study can save approximately $110 million, compared to the baseline, in facility, transportation, and interim storage costs through the year 2013. 10 figs., 28 tabs
Combustion and fuel loading characteristics of Hanford Site transuranic solid waste

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1994-01-01

The Waste Receiving and Processing (WRAP) Facility is being designed for construction in the north end of the Central Waste Complex. The WRAP Facility will receive, store, and process radioactive solid waste of both transuranic (TRU) and mixed waste (mixed radioactive-chemical waste) categories. Most of the waste is in 208-L (55-gal) steel drums. Other containers such as wood and steel boxes, and various sized drums will also be processed in the facility. The largest volume of waste and the type addressed in this report is TRU in 208-L (55-gal) drums that is scheduled to be processed in the Waste Receiving and Processing Facility Module 1 (WRAP 1). Half of the TRU waste processed by WRAP 1 is expected to be retrieved stored waste and the other half newly generated waste. Both the stored and new waste will be processed to certify it for permanent storage in the Waste Isolation Pilot Plant (WIPP) or disposal. The stored waste will go through a process of retrieval, examination, analysis, segregation, repackaging, relabeling, and documentation before certification and WIPP shipment. Newly generated waste should be much easier to process and certify. However, a substantial number of drums of both retrievable and newly generated waste will require temporary storage and handling in WRAP. Most of the TRU waste is combustible or has combustible components. Therefore, the presence of a substantial volume of drummed combustible waste raises concern about fire safety in WRAP and similar waste drum storage facilities. This report analyzes the fire related characteristics of the expected WRAP TRU waste stream
Los Alamos National Laboratory transuranic waste characterization and certification program - an overview of capabilities and capacity

International Nuclear Information System (INIS)

Rogers, P.S.Z.; Sinkule, B.J.; Janecky, D.R.; Gavett, M.A.

1997-01-01

The Los Alamos National Laboratory (LANL) has full capability to characterize transuranic (TRU) waste for shipment to and disposal at the Waste Isolation Pilot Plant (WIPP) for its projected opening. LANL TRU waste management operations also include facilities to repackage both drums of waste found not to be certifiable for WIPP and oversized boxes of waste that must be size reduced for shipment to WIPP. All characterization activities and repackaging are carried out under a quality assurance program designed to meet Carlsbad Area Office (CAO) requirements. The flow of waste containers through characterization operations, the facilities used for characterization, and the electronic data management system used for data package preparation and certification of TRU waste at LANL are described
76 FR 74709 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Final Exclusion

Science.gov (United States)

2011-12-01

..., including any sludge, spill residue, ash, emission control dust, or leachate, remains a hazardous waste... water for use as a cleaning agent. The slop oil waste is thereby diluted and hazardous constituents are... separation sludges that are listed as hazardous wastes due to benzene, benzo(a)pyrene, chrysene, lead and...
Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

Energy Technology Data Exchange (ETDEWEB)

Adkins, H.E.

1996-10-29

This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.
Evaluation of alternatives for high-level and transuranic radioactive- waste disposal standards

International Nuclear Information System (INIS)

Klett, R.D.; Gruebel, M.M.

1992-12-01

The remand of the US Environmental Protection Agency's long-term performance standards for radioactive-waste disposal provides an opportunity to suggest modifications that would make the regulation more defensible and remove inconsistencies yet retain the basic structure of the original rule. Proposed modifications are in three specific areas: release and dose limits, probabilistic containment requirements, and transuranic-waste disposal criteria. Examination of the modifications includes discussion of the alternatives, demonstration of methods of development and implementation, comparison of the characteristics, attributes, and deficiencies of possible options within each area, and analysis of the implications for performance assessments. An additional consideration is the impact on the entire regulation when developing or modifying the individual components of the radiological standards
75 FR 61356 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Correction

Science.gov (United States)

2010-10-05

... Waste Management System; Identification and Listing of Hazardous Waste; Correction AGENCY: Environmental... thermal desorber residual solids with Hazardous Waste Numbers: F037, F038, K048, K049, K050, and K051. In... and correcting it in Table 1 of appendix IX to part 261--Waste Excluded Under Sec. Sec. 260.20 and 260...
Training waste generators: The first responder in proper waste management

International Nuclear Information System (INIS)

Jones, E.

1989-01-01

Dealing with waste effectively requires a ''cradle to grave'' approach to waste management. The first step in that chain of custody is the waste generator. The waste generator plays the key role in the correct identification, packaging, and disposal of waste. The Technical Resources and Training Section at the Oak Ridge National Laboratory (ORNL) has developed several short training programs for waste generators. This training presents a consistent approach to proper handling of waste within the ORNL waste management system. This training has been developed for generators of solid low-level radioactive waste, hazardous and mixed waste, and transuranic waste. In addition to the above, a Waste Minimization training program has been developed for use by all organizations at ORNL who generate any type of hazardous waste. These training programs represent a combined effort of the training staff and the technical staff to assure that all ORNL staff accept their responsibility for handling all types of radioactive and hazardous wastes correctly from its generation to its disposal. 4 refs

Rheological evaluation of simulated neutralized current acid waste - transuranics

International Nuclear Information System (INIS)

Fow, C.L.; McCarthy, D.; Thornton, G.T.; Scott, P.A.; Bray, L.A.

1986-09-01

At the Hanford Plutonium and Uranium Extraction Plant (PUREX), in Richland, Washington, plutonium and uranium products are recovered from irradiated fuel by a solvent extraction process. A byproduct of this process is an aqueous waste stream that contains fission products. This waste stream, called current acid waste (CAW), is chemically neutralized and stored in double shell tanks (DSTs) on the Hanford Site. This neutralized current acid waste (NCAW) will be transported by pipe to B-Plant, a processing plant located nearby. In B-Plant, the transuranic (TRU) elements in NCAW are separated from the non-TRU elements. The majority of the TRU elements in NCAW are in the solids. Therefore, the primary processing operation is to separate the NCAW solids (NCAW-TRU) from the NCAW liquid. These two waste streams will be pumped to suitable holding tanks before being further processed for permanent disposal. To ensure that the retrieval and transportation of NCAW and NCAW-TRU are successful, researchers at Pacific Northwest Laboratory (PNL) evaluated the rheological and transport properties of the slurries. This evaluation had two phases. First, researchers conducted laboratory rheological evaluations of simulated NCAW and NCAW-TRU. The results of these evaluations were then correlated with classical rheological models and scaled up to predict the performance that is likely to occur in the full-scale system. This scale-up procedure has already been successfully used to predict the critical transport properties of a slurry (Neutralized Cladding Removal Waste) with rheological properties similar to those displayed by NCAW and NCAW-TRU
Identification of the fast and thermal neutron characteristics of transuranic waste drums

Energy Technology Data Exchange (ETDEWEB)

Storm, B.H. Jr.; Bramblett, R.L. [Lockheed Martin Specialty Components, Largo, FL (United States); Hensley, C. [Oak Ridge National Lab., TN (United States)

1997-11-01

Fissile and spontaneously fissioning material in transuranic waste drums can be most sensitively assayed using an active and passive neutron assay system such as the Active Passive Neutron Examination and Assay. Both the active and the passive assays are distorted by the presence of the waste matrix and containerization. For accurate assaying, this distortion must be characterized and accounted for. An External Matrix Probe technique has been developed that accomplishes this task. Correlations between in-drum neutron flux measurements and monitors in the Active Passive Neutron Examination and Assay chamber with various matrix materials provide a non-invasive means of predicting the thermal neutron flux in waste drums. Similarly, measures of the transmission of fast neutrons emitted from sources in the drum. Results obtained using the Lockheed Martin Specialty Components Active Passive Neutron Examination and Assay system are discussed. 12 figs., 1 tab.
Comprehensive implementation plan for the DOE defense buried TRU- contaminated waste program

International Nuclear Information System (INIS)

Everette, S.E.; Detamore, J.A.; Raudenbush, M.H.; Thieme, R.E.

1988-02-01

In 1970, the US Atomic Energy Commission established a ''transuranic'' (TRU) waste classification. Waste disposed of prior to the decision to retrievably store the waste and which may contain TRU contamination is referred to as ''buried transuranic-contaminated waste'' (BTW). The DOE reference plan for BTW, stated in the Defense Waste Management Plan, is to monitor it, to take such remedial actions as may be necessary, and to re-evaluate its safety as necessary or in about 10-year periods. Responsibility for management of radioactive waste and byproducts generated by DOE belongs to the Secretary of Energy. Regulatory control for these sites containing mixed waste is exercised by both DOE (radionuclides) and EPA (hazardous constituents). Each DOE Operations Office is responsible for developing and implementing plans for long-term management of its radioactive and hazardous waste sites. This comprehensive plan includes site-by-site long-range plans, site characteristics, site costs, and schedules at each site. 13 figs., 15 tabs
Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

Energy Technology Data Exchange (ETDEWEB)

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.
Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240

Energy Technology Data Exchange (ETDEWEB)

Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

2013-07-01

Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m{sup 3} (55-gal) drum which contains either a 0.04 m{sup 3} or 0.06 m{sup 3} (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ∼12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated
Hazardous waste: cleanup and prevention

Science.gov (United States)

Vandas, Stephen; Cronin, Nancy L.; Farrar, Frank; Serrano, Guillermo Eliezer Ávila; Yajimovich, Oscar Efraín González; Muñoz, Aurora R.; Rivera, María del C.

1996-01-01

Our lifestyles are supported by complex Industrial activities that produce many different chemicals and chemical wastes. The Industries that produce our clothing, cars, medicines, paper, food, fuels, steel, plastics, and electric components use and discard thousands of chemicals every year. At home we may use lawn chemicals, solvents, disinfectants, cleaners, and auto products to Improve our quality of life. A chemical that presents a threat or unreasonable risk to people or the environment Is a hazardous material. When a hazardous material can no longer be used, It becomes a hazardous waste. Hazardous wastes come from a variety of sources, from both present and past activities. Impacts to human health and the environment can result from Improper handling and disposal of hazardous waste.
75 FR 60689 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Proposed Rule

Science.gov (United States)

2010-10-01

... Waste Management System; Identification and Listing of Hazardous Waste; Proposed Rule AGENCY... exclude (or delist) a certain solid waste generated by its Beaumont, Texas, facility from the lists of hazardous wastes. EPA used the Delisting Risk Assessment Software (DRAS) Version 3.0 in the evaluation of...
Hazardous Waste Cerification Plan: Hazardous Waste Handling Facility, Lawrence Berkeley Laboratory

International Nuclear Information System (INIS)

1992-02-01

The purpose of this plan is to describe the organization and methodology for the certification of hazardous waste (HW) handled in the Lawrence Berkeley Laboratory (LBL) Hazardous Waste Handling Facility (HWHF). The 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; and executive summary of the Quality Assurance Program Plan (QAPP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. The plan provides guidance from the HWHF to waste generators, waste handlers, and the Systems Group Manager to enable them to conduct their activities and carry out their responsibilities in a manner that complies with several requirements of the Federal Resource Conservation and Resource Recovery Act (RCRA), the Federal Department of Transportation (DOT), and the State of California, Code of Regulations (CCR), Title 22
Plutonium and other transuranics in small vertebrates: a review

International Nuclear Information System (INIS)

Bradley, W.G.; Moor, K.S.; Naegle, S.R.

1977-01-01

The published data relevant to transuranics in small vertebrates inhabiting terrestrial environments is reviewed. Experimental results indicate that atomic size and valence state affect rates of absorption, transportation, and excretion of transuranics in living systems. Whereas there is a marked tendency for transuranics to hydrolyze to insoluble colloidal products at physiological pH, complexing agents and chelation enhance solubility and transportability. The natural modes of uptake of transuranics by vertebrates include absorption from the gut, the intact or damaged skin, and inhalation. Absorption from the gut into the bloodstream is very low. Potential hazards may exist if complexing or chelating agents are present, if absorption is continuous, or if exposure involves young animals. The intact skin provides an effective barrier to absorption of transuranics. Relatively high levels of absorption may occur when transuranics are administered subcutaneously or intramuscularly, particularly with increased acidity and solubility of the compounds. Inhalation is probably the most hazardous natural route of uptake. Insoluble transuranic compounds are retained in the lung and soluble compounds are transported rapidly via the blood to bone, liver, and other organs. Deposition of plutonium in mammalian gonads resulting in a decrease in spermatogenesis, ovarian damage, and reduced fecundity is documented. The current knowledge of the behavior of transuranics in terrestrial environments is limited. Plutonium and americium uptake by small mammals has been documented. Plutonium body burdens were related to depressed leukocyte count on a statistical basis. Reduced rodent populations in areas of high plutonium concentrations illustrate the problems of evaluating uptake by mobile animals
The TRUEX [TRansUranium EXtraction] process and the management of liquid TRU [transuranic] waste

International Nuclear Information System (INIS)

Schulz, W.W.; Horwitz, E.P.

1987-01-01

The TRUEX process is a new generic liquid-liquid extraction process for removal of all actinides from acidic nitrate or chloride nuclear waste solutions. Because of its high efficiency and great flexibility, the TRUEX process appears destined to be widely used in the US and possibly in other countries for cost-effective management and disposal of transuranic (TRU) wastes. In the US, TRU wastes are those that contain ≥3.7 x 10 6 Bq/kg) of TRU elements with half-lives greater than 20 y. This paper gives a brief review of the relevant chemistry and summarizes the current status of development and deployment of the TRUEX (TRansUranium EXtraction) process flowsheets to treat specific acidic waste solutions at several US Department of Energy sites. 19 refs., 4 figs., 4 tabs
INTERNATIONAL UNION OF OPERATING ENGINEERS NATIONAL HAZMAT PROGRAM - HANDSS-55 TRANSURANIC WASTE REPACKAGING MODULE

International Nuclear Information System (INIS)

2001-01-01

The Transuranic waste generated at the Savannah River Site from nuclear weapons research, development, and production is currently estimated to be over 10,000 cubic meters. Over half of this amount is stored in 55-gallon drums. The waste in drums is primarily job control waste and equipment generated as the result of routine maintenance performed on the plutonium processing operations. Over the years that the drums have been accumulating, the regulatory definitions of materials approved for disposal have changed. Consequently, many of the drums now contain items that are not approved for disposal at DOE Waste Isolation Pilot Plant (WIPP). The HANDSS-55 technology is being developed to allow remote sorting of the items in these drums and then repackaging of the compliant items for disposal at WIPP
Hazardous waste management in the Pacific basin

Energy Technology Data Exchange (ETDEWEB)

Cirillo, R.R.; Chiu, S.; Chun, K.C.; Conzelmann, G. [Argonne National Lab., IL (United States); Carpenter, R.A.; Indriyanto, S.H. [East-West Center, Honolulu, HI (United States)

1994-11-01

Hazardous waste control activities in Asia and the Pacific have been reviewed. The review includes China (mainland, Hong Kong, and Taiwan), Indonesia, Korea, Malaysia, Papua New Guinea, the Philippines, Singapore, and Thailand. It covers the sources of hazardous waste, the government structure for dealing with hazardous waste, and current hazardous waste control activities in each country. In addition, the hazardous waste program activities of US government agencies, US private-sector organizations, and international organizations are reviewed. The objective of these reviews is to provide a comprehensive picture of the current hazardous waste problems and the waste management approaches being used to address them so that new program activities can be designed more efficiently.
The Hazardous Waste/Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

Bailey, L.L.

1991-01-01

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996
Hazardous constituent source term. Revision 2

International Nuclear Information System (INIS)

1994-01-01

The Department of Energy (DOE) has several facilities that either generate and/or store transuranic (TRU)-waste from weapons program research and production. Much of this waste also contains hazardous waste constituents as regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA). Toxicity characteristic metals in the waste principally include lead, occurring in leaded rubber gloves and shielding. Other RCRA metals may occur as contaminants in pyrochemical salt, soil, debris, and sludge and solidified liquids, as well as in equipment resulting from decontamination and decommissioning activities. Volatile organic compounds (VOCS) contaminate many waste forms as a residue adsorbed on surfaces or occur in sludge and solidified liquids. Due to the presence of these hazardous constituents, applicable disposal regulations include land disposal restrictions established by Hazardous and Solid Waste Amendments (HSWA). The DOE plans to dispose of TRU-mixed waste from the weapons program in the Waste Isolation Pilot Plant (WIPP) by demonstrating no-migration of hazardous constituents. This paper documents the current technical basis for methodologies proposed to develop a post-closure RCRA hazardous constituent source term. For the purposes of demonstrating no-migration, the hazardous constituent source term is defined as the quantities of hazardous constituents that are available for transport after repository closure. Development of the source term is only one of several activities that will be involved in the no-migration demonstration. The demonstration will also include uncertainty and sensitivity analyses of contaminant transport
Results from simulated contact-handled transuranic waste experiments at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Molecke, M.A.; Sorensen, N.R.; Krumhansl, J.L.

1993-01-01

We conducted in situ experiments with nonradioactive, contact-handled transuranic (CH TRU) waste drums at the Waste Isolation Pilot Plant (WIPP) facility for about four years. We performed these tests in two rooms in rock salt, at WIPP, with drums surrounded by crushed salt or 70 wt % salt/30 wt % bentonite clay backfills, or partially submerged in a NaCl brine pool. Air and brine temperatures were maintained at ∼40C. These full-scale (210-L drum) experiments provided in situ data on: backfill material moisture-sorption and physical properties in the presence of brine; waste container corrosion adequacy; and, migration of chemical tracers (nonradioactive actinide and fission product simulants) in the near-field vicinity, all as a function of time. Individual drums, backfill, and brine samples were removed periodically for laboratory evaluations. Waste container testing in the presence of brine and brine-moistened backfill materials served as a severe overtest of long-term conditions that could be anticipated in an actual salt waste repository. We also obtained relevant operational-test emplacement and retrieval experience. All test results are intended to support both the acceptance of actual TRU wastes at the WIPP and performance assessment data needs. We provide an overview and technical data summary focusing on the WIPP CH TRU envirorunental overtests involving 174 waste drums in the presence of backfill materials and the brine pool, with posttest laboratory materials analyses of backfill sorbed-moisture content, CH TRU drum corrosion, tracer migration, and associated test observations
Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

Energy Technology Data Exchange (ETDEWEB)

Martell, M.A.; Hansen, F.; Weiner, R.

1998-10-01

Use of nature`s laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia.
Hazardous waste minimization tracking system

International Nuclear Information System (INIS)

Railan, R.

1994-01-01

Under RCRA section 3002 9(b) and 3005f(h), hazardous waste generators and owners/operators of treatment, storage, and disposal facilities (TSDFs) are required to certify that they have a program in place to reduce the volume or quantity and toxicity of hazardous waste to the degree determined to be economically practicable. In many cases, there are environmental, as well as, economic benefits, for agencies that pursue pollution prevention options. Several state governments have already enacted waste minimization legislation (e.g., Massachusetts Toxic Use Reduction Act of 1989, and Oregon Toxic Use Reduction Act and Hazardous Waste Reduction Act, July 2, 1989). About twenty six other states have established legislation that will mandate some type of waste minimization program and/or facility planning. The need to address the HAZMIN (Hazardous Waste Minimization) Program at government agencies and private industries has prompted us to identify the importance of managing The HAZMIN Program, and tracking various aspects of the program, as well as the progress made in this area. The open-quotes WASTEclose quotes is a tracking system, which can be used and modified in maintaining the information related to Hazardous Waste Minimization Program, in a manageable fashion. This program maintains, modifies, and retrieves information related to hazardous waste minimization and recycling, and provides automated report generating capabilities. It has a built-in menu, which can be printed either in part or in full. There are instructions on preparing The Annual Waste Report, and The Annual Recycling Report. The program is very user friendly. This program is available in 3.5 inch or 5 1/4 inch floppy disks. A computer with 640K memory is required
Portable sensor for hazardous waste

International Nuclear Information System (INIS)

Piper, L.G.

1994-01-01

Objective was to develop a field-portable monitor for sensitive hazardous waste detection using active nitrogen energy transfer (ANET) excitation of atomic and molecular fluorescence (active nitrogen is made in a dielectric-barrier discharge in nitrogen). It should provide rapid field screening of hazardous waste sites to map areas of greatest contamination. Results indicate that ANET is very sensitive for monitoring heavy metals (Hg, Se) and hydrocarbons; furthermore, chlorinated hydrocarbons can be distinguished from nonchlorinated ones. Sensitivity is at ppB levels for sampling in air. ANET appears ideal for on-line monitoring of toxic heavy metal levels at building sites, hazardous waste land fills, in combustor flues, and of chlorinated hydrocarbon levels at building sites and hazardous waste dumps
Transuranic solid waste management research programs. Progress report, January--June 1975

International Nuclear Information System (INIS)

1976-03-01

Tests continued to evaluate less costly fiber drums as alternate storage containers for low-level wastes. Tests completed to date indicated that the factory-applied fire retardants were not satisfactory; however, investigations of more promising coatings have been undertaken. The fiber drums were more satisfactory in other aspects. Expanded laboratory and field radiolysis experiments were performed. These were accompanied by investigations of H 2 diffusion through common waste packaging materials and through Los Alamos soil. Radiolysis studies were also initiated on wastes typical of Mound Laboratory. All results to date show that while H 2 is being slowly generated, the quantities are not excessive and should diffuse rapidly away. Construction of the TDF facility began and was 14 percent complete at the end of this reporting period. The incinerator was received, installed and checked out, and is operational. Additional specifications were developed and equipment procurement continued. Progress is reported on development of a system for evaluating radioactively contaminated solid waste burial sites. Source term data are summarized for some Los Alamos areas along with waste composition and configuration considerations. Physical and biotic transport pathways are discussed and development of modeling methods for projecting the environmental fate of transuranic materials is detailed
Transuranic solid waste management research programs. Progress report, January--June 1975

Energy Technology Data Exchange (ETDEWEB)

1976-03-01

Tests continued to evaluate less costly fiber drums as alternate storage containers for low-level wastes. Tests completed to date indicated that the factory-applied fire retardants were not satisfactory; however, investigations of more promising coatings have been undertaken. The fiber drums were more satisfactory in other aspects. Expanded laboratory and field radiolysis experiments were performed. These were accompanied by investigations of H/sub 2/ diffusion through common waste packaging materials and through Los Alamos soil. Radiolysis studies were also initiated on wastes typical of Mound Laboratory. All results to date show that while H/sub 2/ is being slowly generated, the quantities are not excessive and should diffuse rapidly away. Construction of the TDF facility began and was 14 percent complete at the end of this reporting period. The incinerator was received, installed and checked out, and is operational. Additional specifications were developed and equipment procurement continued. Progress is reported on development of a system for evaluating radioactively contaminated solid waste burial sites. Source term data are summarized for some Los Alamos areas along with waste composition and configuration considerations. Physical and biotic transport pathways are discussed and development of modeling methods for projecting the environmental fate of transuranic materials is detailed.

Proceedings of the second FY87 meeting of the National Working Group for Reduction in Transuranic Waste Arisings

International Nuclear Information System (INIS)

1987-09-01

The Second FY87 Meeting of the National Working Group for Reduction in Transuranic Waste Arisings (NWGRTWA) was held at the Lawrence Livermore National Laboratory, Tuesday and Wednesday, July 28--29, 1987. The purpose of the meeting was to discuss (1) modeling programs for waste reduction, (2) proposed FY88 and out-year tasks including the SRL Pu incineration, immobilization improvement, erbia coating technology, and (3) improvements in up-stream recovery operations to effect waste reduction. In addition, tours were made of the LLNL Waste Operations, the Laser Fusion (NOVA), and the Magnetic Fusion (MFTF)
Energy and solid/hazardous waste

Energy Technology Data Exchange (ETDEWEB)

None

1981-12-01

This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included. (PSB)
Energy and solid/hazardous waste

International Nuclear Information System (INIS)

1981-12-01

This report addresses the past and potential future solid and hazardous waste impacts from energy development, and summarizes the major environmental, legislation applicable to solid and hazardous waste generation and disposal. A glossary of terms and acronyms used to describe and measure solid waste impacts of energy development is included
Technologies to remediate hazardous waste sites

International Nuclear Information System (INIS)

Falco, J.W.

1990-03-01

Technologies to remediate hazardous wastes must be matched with the properties of the hazardous materials to be treated, the environment in which the wastes are imbedded, and the desired extent of remediation. Many promising technologies are being developed, including biological treatment, immobilization techniques, and in situ methods. Many of these new technologies are being applied to remediate sites. The management and disposal of hazardous wastes is changing because of federal and state legislation as well as public concern. Future waste management systems will emphasize the substitution of alternatives for the use of hazardous materials and process waste recycling. Onsite treatment will also become more frequently adopted. 5 refs., 7 figs
Cost-benefit analysis for waste compaction alternatives at Lawrence Livermore National Laboratory: Addendum A to the Waste Minimization and Pollution Prevention Awareness Plan of May 31, 1991

International Nuclear Information System (INIS)

1992-01-01

This report presents a cost-benefit analysis of the potential procurement and operation of various solid waste compactors or of the use of commercial compaction services, for compaction of solid transuranic (TRU), low-level radioactive, hazardous, and mixed wastes at Lawrence Livermore National Laboratory (LLNL) Hazardous Waste Management (HWM) facilities. The cost-benefit analysis was conducted to determine if increased compaction capacity at HWM might afford the potential for significant waste volume reduction and annual savings in material, shipping, labor, and disposal costs
75 FR 78918 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Removal of...

Science.gov (United States)

2010-12-17

... and Community Right-to-Know Act FDA Food and Drug Administration HSWA Hazardous and Solid Waste...(f)), and hazardous substances (40 CFR 302.4) based solely upon the evidence that it is a potential... subsequently identified as hazardous wastes in Sec. 261.33(f) based solely on their potential for carcinogenic...
Physical Properties of Hanford Transuranic Waste Sludge

International Nuclear Information System (INIS)

Poloski, A. P.

2004-01-01

This project has two primary objectives. The first is to understand the physical properties and behavior of the Hanford transuranic (TRU) tank sludges under conditions that might exist during retrieval, treatment, packaging, and transportation for disposal at WIPP. The second primary objective is to develop a fundamental understanding of these sludge suspensions by correlating the macroscopic properties with particle interactions occurring at the colloidal scale in the various liquid media. The results of this research effort will enhance the existing understanding of agglomeration phenomena and the properties of complex colloidal suspensions. In addition, the knowledge gained and capabilities developed during this effort will aid in the development and optimization of techniques to process the wastes at various DOE sites. These objectives will be accomplished by: (1) characterizing the TRU sludges contained in the Hanford tanks that are intended for shipment to WIPP; (2) determining the physical behavior of the Hanford TRU tank sludges under conditions that might exist during treatment and packaging; (3) and modeling the retrieval, treatment, and packaging operations that will be performed at Hanford to dispose of TRU tank sludges
Concentration of remote-handled, transuranic, sodium nitrate-based sludge using agitated thin-film evaporators

International Nuclear Information System (INIS)

Walker, J.F. Jr.; Youngblood, E.L.; Berry, J.B.; Pen, Ben-Li

1991-01-01

The Waste Handling and Packaging Plant (WHPP) is being designed at Oak Ridge National Laboratory (ORNL) to prepared transuranic waste for final disposal. Once operational, this facility will process, package, and certify remote-handled transuranic waste for ultimate shipment and disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. One of the wastes that will be handled at WHIPP is the transuranic sludge currently stored at ORNL in eight 50,000-gal underground tanks. The use of an Agitated Thin-Film Evaporator (ATFE) for concentration of this waste is being investigated. Tests have shown that the ATFE can be used to produce a thick slurry, a powder, or a fused salt. A computer model developed at the Savannah River Plant (SRP) to simulate the operation of ATFE's on their waste is being modified for use on the ORNL transuranic sludge. This paper summarizes the results of the test with the ATFEs to date, discusses the changes in the SRP model necessary to use this model with the ORNL waste, and compares the results of the model with the actual data taken from the operation of ATFEs at vendors' test facilities. 8 refs., 1 fig., 3 tabs
75 FR 67919 - Hazardous Waste Management System; Proposed Exclusion for Identifying and Listing Hazardous Waste

Science.gov (United States)

2010-11-04

... treatment sludge from the lists of hazardous waste set forth in Title 40 of the Code of Federal Regulations... treatment sludges generated at its facility located in Owosso, Michigan from the list of hazardous wastes... disposed in a Subtitle D landfill and we considered transport of waste constituents through ground water...
Risk perception on management of nuclear high-level and transuranic waste storage

Energy Technology Data Exchange (ETDEWEB)

Dees, Lawrence A. [Colorado Christian Univ., Lakewood, CO (United States)

1994-08-15

The Department of Energy`s program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE`s management plans for with nuclear HLW and TRU waste disposal. Postponing the permanent geologic repository and use of Monitored Retrievable Storage (MRS) would provide the time necessary for difficult social and political issues to be resolved. It would also allow time for the public to become better educated if DOE chooses to become proactive.
Risk perception on management of nuclear high-level and transuranic waste storage

International Nuclear Information System (INIS)

Dees, L.A.

1994-01-01

The Department of Energy's program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE's management plans for with nuclear HLW and TRU waste disposal. Postponing the permanent geologic repository and use of Monitored Retrievable Storage (MRS) would provide the time necessary for difficult social and political issues to be resolved. It would also allow time for the public to become better educated if DOE chooses to become proactive
40 CFR 270.62 - Hazardous waste incinerator permits.

Science.gov (United States)

2010-07-01

... WASTES (CONTINUED) EPA ADMINISTERED PERMIT PROGRAMS: THE HAZARDOUS WASTE PERMIT PROGRAM Special Forms of Permits § 270.62 Hazardous waste incinerator permits. When an owner or operator of a hazardous waste... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Hazardous waste incinerator permits...
DOE assay methods used for characterization of contact-handled transuranic waste

Energy Technology Data Exchange (ETDEWEB)

Schultz, F.J. (Oak Ridge National Lab., TN (United States)); Caldwell, J.T. (Pajarito Scientific Corp., Los Alamos, NM (United States))

1991-08-01

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs.
DOE assay methods used for characterization of contact-handled transuranic waste

International Nuclear Information System (INIS)

Schultz, F.J.; Caldwell, J.T.

1991-08-01

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs
Hazardous Waste: Learn the Basics of Hazardous Waste

Science.gov (United States)

... Need More Information on Hazardous Waste? The RCRA Orientation Manual provides introductory information on the solid and ... and Security Notice Connect. Data.gov Inspector General Jobs Newsroom Open Government Regulations.gov Subscribe USA.gov ...
Transuranic and Low-Level Boxed Waste Form Nondestructive Assay Technology Overview and Assessment

International Nuclear Information System (INIS)

Becker, G.; Connolly, M.; McIlwain, M.

1999-01-01

The Mixed Waste Focus Area (MWFA) identified the need to perform an assessment of the functionality and performance of existing nondestructive assay (NDA) techniques relative to the low-level and transuranic waste inventory packaged in large-volume box-type containers. The primary objectives of this assessment were to: (1) determine the capability of existing boxed waste form NDA technology to comply with applicable waste radiological characterization requirements, (2) determine deficiencies associated with existing boxed waste assay technology implementation strategies, and (3) recommend a path forward for future technology development activities, if required. Based on this assessment, it is recommended that a boxed waste NDA development and demonstration project that expands the existing boxed waste NDA capability to accommodate the indicated deficiency set be implemented. To ensure that technology will be commercially available in a timely fashion, it is recommended this development and demonstration project be directed to the private sector. It is further recommended that the box NDA technology be of an innovative design incorporating sufficient NDA modalities, e.g., passive neutron, gamma, etc., to address the majority of the boxed waste inventory. The overall design should be modular such that subsets of the overall NDA system can be combined in optimal configurations tailored to differing waste types
Sampling and analysis validates acceptable knowledge on LANL transuranic, heterogeneous, debris waste, or ''Cutting the Gordian knot that binds WIPP''

International Nuclear Information System (INIS)

Kosiewicz, S.T.; Triay, I.R.; Souza, L.A.

1999-01-01

Through sampling and toxicity characteristic leaching procedure (TCLP) analyses, LANL and the DOE validated that a LANL transuranic (TRU) waste (TA-55-43, Lot No. 01) was not a Resource Recovery and Conservation Act (RCRA) hazardous waste. This paper describes the sampling and analysis project as well as the statistical assessment of the analytical results. The analyses were conducted according to the requirements and procedures in the sampling and analysis plan approved by the New Mexico Environmental Department. The plan used a statistical approach that was consistent with the stratified, random sampling requirements of SW-846. LANL adhered to the plan during sampling and chemical analysis of randomly selected items of the five major types of materials in this heterogeneous, radioactive, debris waste. To generate portions of the plan, LANL analyzed a number of non-radioactive items that were representative of the mix of items present in the waste stream. Data from these cold surrogates were used to generate means and variances needed to optimize the design. Based on statistical arguments alone, only two samples from the entire waste stream were deemed necessary, however a decision was made to analyze at least two samples of each of the five major waste types. To obtain these samples, nine TRU waste drums were opened. Sixty-six radioactively contaminated and four non-radioactive grab samples were collected. Portions of the samples were composited for chemical analyses. In addition, a radioactively contaminated sample of rust-colored powder of interest to the New Mexico Environment Department (NMED) was collected and qualitatively identified as rust
Central waste complex interim safety basis

International Nuclear Information System (INIS)

Cain, F.G.

1995-01-01

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste
Hazardous waste sites and housing appreciation rates

OpenAIRE

McCluskey, Jill Jennifer; Rausser, Gordon C

2000-01-01

The dynamic effect of a hazardous waste site is analyzed by investigating the causal relationship between housing appreciation rates and house location in relation to a hazardous waste site using resale data from individual sales transactions in Dallas County, Texas. The results indicate that in the period in which the hazardous waste site was identified and cleanup occurred, residential property owners in close proximity to the hazardous waste site experienced lower housing appreciation rate...
Hot Cell Liners Category of Transuranic Waste Stored Below Ground within Area G

Energy Technology Data Exchange (ETDEWEB)

Jones, Robert Wesley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-09-01

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is an agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Hot Cell Liners category; their physical and radiological characteristics; the results of the radioassays; and the justification to reclassify the five containers as LLW rather than TRU waste.

Treatment of hazardous metals by in situ vitrification

International Nuclear Information System (INIS)

Koegler, S.S.; Buelt, J.L.

1989-02-01

Soils contaminated with hazardous metals are a significant problem to many Defense Program sites. Contaminated soils have ranked high in assessments of research and development needs conducted by the Hazardous Waste Remedial Action Program (HAZWRAP) in FY 1988 and FY 1989. In situ vitrification (ISV) is an innovative technology suitable for stabilizing soils contaminated with radionuclides and hazardous materials. Since ISV treats the material in place, it avoids costly and hazardous preprocessing exhumation of waste. In situ vitrification was originally developed for immobilizing radioactive (primarily transuranic) soil constituents. Tests indicate that it is highly useful also for treating other soil contaminants, including hazardous metals. The ISV process produces an environmentally acceptable, highly durable glasslike product. In addition, ISV includes an efficient off-gas treatment system that eliminates noxious gaseous emissions and generates minimal hazardous byproducts. This document reviews the Technical Basis of this technology. 5 refs., 7 figs., 2 tabs
Summary of Remediated and Unremediated Nitrate Salt Surrogate Testing in Support of the Waste Treatment Permit Application to the New Mexico Environment Department (NMED)

Energy Technology Data Exchange (ETDEWEB)

Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-06-22

The inadvertent creation of transuranic waste carrying hazardous waste codes D001 and D002 requires the treatment of the material to eliminate the hazardous characteristics and allow its eventual shipment and disposal at the Waste Isolation Pilot Plant (WIPP). This report briefly summarizes the surrogate testing that was done in support of our understanding of this waste form.
Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Rempe, N.T.

1993-01-01

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

Energy Technology Data Exchange (ETDEWEB)

Krause, Max J.; Townsend, Timothy G., E-mail: ttown@ufl.edu

2015-05-15

Highlights: • Electronic cigarettes were tested using TCLP and WET. • Several electronic cigarette products leached lead at hazardous waste levels. • Lead was the only element that exceeded hazardous waste concentration thresholds. • Nicotine solution may cause hazardous waste classification when discarded unused. - Abstract: The potential for disposable electronic cigarettes (e-cigarettes) to be classified as hazardous waste was investigated. The Toxicity Characteristic Leaching Procedure (TCLP) was performed on 23 disposable e-cigarettes in a preliminary survey of metal leaching. Based on these results, four e-cigarette products were selected for replicate analysis by TCLP and the California Waste Extraction Test (WET). Lead was measured in leachate as high as 50 mg/L by WET and 40 mg/L by TCLP. Regulatory thresholds were exceeded by two of 15 products tested in total. Therefore, some e-cigarettes would be toxicity characteristic (TC) hazardous waste but a majority would not. When disposed in the unused form, e-cigarettes containing nicotine juice would be commercial chemical products (CCP) and would, in the United States (US), be considered a listed hazardous waste (P075). While household waste is exempt from hazardous waste regulation, there are many instances in which such waste would be subject to regulation. Manufactures and retailers with unused or expired e-cigarettes or nicotine juice solution would be required to manage these as hazardous waste upon disposal. Current regulations and policies regarding the availability of nicotine-containing e-cigarettes worldwide were reviewed. Despite their small size, disposable e-cigarettes are consumed and discarded much more quickly than typical electronics, which may become a growing concern for waste managers.
Hazardous waste status of discarded electronic cigarettes

International Nuclear Information System (INIS)

Krause, Max J.; Townsend, Timothy G.

2015-01-01

Highlights: • Electronic cigarettes were tested using TCLP and WET. • Several electronic cigarette products leached lead at hazardous waste levels. • Lead was the only element that exceeded hazardous waste concentration thresholds. • Nicotine solution may cause hazardous waste classification when discarded unused. - Abstract: The potential for disposable electronic cigarettes (e-cigarettes) to be classified as hazardous waste was investigated. The Toxicity Characteristic Leaching Procedure (TCLP) was performed on 23 disposable e-cigarettes in a preliminary survey of metal leaching. Based on these results, four e-cigarette products were selected for replicate analysis by TCLP and the California Waste Extraction Test (WET). Lead was measured in leachate as high as 50 mg/L by WET and 40 mg/L by TCLP. Regulatory thresholds were exceeded by two of 15 products tested in total. Therefore, some e-cigarettes would be toxicity characteristic (TC) hazardous waste but a majority would not. When disposed in the unused form, e-cigarettes containing nicotine juice would be commercial chemical products (CCP) and would, in the United States (US), be considered a listed hazardous waste (P075). While household waste is exempt from hazardous waste regulation, there are many instances in which such waste would be subject to regulation. Manufactures and retailers with unused or expired e-cigarettes or nicotine juice solution would be required to manage these as hazardous waste upon disposal. Current regulations and policies regarding the availability of nicotine-containing e-cigarettes worldwide were reviewed. Despite their small size, disposable e-cigarettes are consumed and discarded much more quickly than typical electronics, which may become a growing concern for waste managers
49 CFR 171.3 - Hazardous waste.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Hazardous waste. 171.3 Section 171.3... waste. (a) No person may offer for transportation or transport a hazardous waste (as defined in § 171.8... waste for which a manifest is required unless that person: (1) Has marked each motor vehicle used to...
Predictions and implications of a poisson process model to describe corrosion of transuranic waste drums

International Nuclear Information System (INIS)

Lyon, B.F.; Holmes, J.A.; Wilbert, K.A.

1995-01-01

A risk assessment methodology is described in this paper to compare risks associated with immediate or near-term retrieval of transuranic (TRU) waste drums from bermed storage versus delayed retrieval. Assuming a Poisson process adequately describes corrosion, significant breaching of drums is expected to begin at - 15 and 24 yr for pitting and general corrosion, respectively. Because of this breaching, more risk will be incurred by delayed than by immediate retrieval
Portable sensor for hazardous waste

Energy Technology Data Exchange (ETDEWEB)

Piper, L.G.; Fraser, M.E.; Davis, S.J. [Physical Sciences Inc., Andover, MA (United States)

1995-10-01

We are beginning the second phase of a three and a half year program designed to develop a portable monitor for sensitive hazardous waste detection. The ultimate goal of the program is to develop our concept to the prototype instrument level. Our monitor will be a compact, portable instrument that will allow real-time, in situ, monitoring of hazardous wastes. This instrument will be able to provide the means for rapid field screening of hazardous waste sites to map the areas of greatest contamination. Remediation efforts can then focus on these areas. Further, our instrument can show whether cleanup technologies are successful at reducing hazardous materials concentrations below regulated levels, and will provide feedback to allow changes in remediation operations, if necessary, to enhance their efficacy.
75 FR 71559 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Withdrawal of...

Science.gov (United States)

2010-11-24

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 261 [EPA-R06-RCRA-2010-0066; SW FRL-9231-4] Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Withdrawal of Direct Final Exclusion AGENCY: Environmental Protection Agency (EPA). ACTION: Withdrawal of direct final exclusion...
Hazardous waste disposal sites: Report 2

International Nuclear Information System (INIS)

1979-12-01

Arkansas, like virtually every other state, is faced with a deluge of hazardous waste. There is a critical need for increased hazardous waste disposal capacity to insure continued industrial development. Additionally, perpetual maintenance of closed hazardous waste disposal sites is essential for the protection of the environment and human health. Brief descriptions of legislative and regulatory action in six other states are provided in this report. A report prepared for the New York State Environmental Facilities Corp. outlines three broad approaches states may take in dealing with their hazardous waste disposal problems. These are described. State assistance in siting and post-closure maintenance, with private ownership of site and facility, appears to be the most advantageous option
Assessment of LANL hazardous waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) ''Hazardous Waste Acceptance Criteria Receipt at TA-54, Area L'' to determine if it meets applicable DOE requirements. The guidelines and requirements for the establishment of a Hazardous Waste Acceptance Criteria (HW-WAC) are found in 40 CFR 260 to 270 and DOE Order 5820.2A. Neither set of requirements specifically require a WAC for the management of hazardous waste; however, the use of such documentation is logical and is consistent with the approach required for the management of radioactive waste. The primary purpose of a HW-WAC is to provide generators and waste management with established criteria that must be met before hazardous waste can be acceptable for treatment, storage and/or disposal. An annotated outline for a generic waste acceptance criteria was developed based on the requirements of 40 CFR 260 to 270 and DOE Order 5820.2A. The outline contains only requirements for hazardous waste, it does not address the radiological components of low-level mixed waste. The outline generated from the regulations was used for comparison to the LANL WAC For Chemical and Low-level Mixed Waste Receipt at TA-54, Area L. The major elements that should be addressed by a hazardous waste WAC were determined to be as follows: Waste Package/Container Requirements, Waste Forms, Land Disposal Restrictions, and Data Package-Certification ampersand Documentation
Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1

International Nuclear Information System (INIS)

1995-09-01

This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond
Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond.
Intermediate depth burial of classified transuranic wastes in arid alluvium

International Nuclear Information System (INIS)

Cochran, J.R.; Crowe, B.M.; Di Sanza, F.

1999-01-01

Intermediate depth disposal operations were conducted by the US Department of Energy (DOE) at the DOE's Nevada Test Site (NTS) from 1984 through 1989. These operations emplaced high-specific activity low-level wastes (LLW) and limited quantities of classified transuranic (TRU) wastes in 37 m (120-ft) deep, Greater Confinement Disposal (GCD) boreholes. The GCD boreholes are 3 m (10 ft) in diameter and founded in a thick sequence of arid alluvium. The bottom 15 m (50 ft) of each borehole was used for waste emplacement and the upper 21 m (70 ft) was backfilled with native alluvium. The bottom of each GCD borehole is almost 200 m (650 ft) above the water table. The GCD boreholes are located in one of the most arid portions of the US, with an average precipitation of 13 cm (5 inches) per year. The limited precipitation, coupled with generally warm temperatures and low humidities results in a hydrologic system dominated by evapotranspiration. The US Environmental Protection Agency's (EPA's) 40 CFR 191 defines the requirements for protection of human health from disposed TRU wastes. This EPA standard sets a number of requirements, including probabilistic limits on the cumulative releases of radionuclides to the accessible environment for 10,000 years. The DOE Nevada Operations Office (DOE/NV) has contracted with Sandia National Laboratories (Sandia) to conduct a performance assessment (PA) to determine if the TRU wastes emplaced in the GCD boreholes complies with the EPA's 40 CFR 191 requirements. This paper describes DOE's actions undertaken to evaluate whether the TRU wastes in the GCD boreholes will, or will not, endanger human health. Based on preliminary modeling, the TRU wastes in the GCD boreholes meet the EPA's requirements, and are, therefore, protective of human health
Criticality safety of transuranic storage arrays at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Boyd, W.A.; Fecteau, M.W.

1993-01-01

The Waste Isolation Pilot Plant (WIPP) facility is designed to store transuranic waste that will consist mainly of surface contaminate articles and sludge. The fissile material in the waste is predominantly 239 Pu. The waste is grouped into two categories: contact-handled waste, which will be stored in 55-gal steel drums or in steel boxes, and remote-handled waste, which will be stored in specially designed cylindrical steel canisters. To show that criticality safety will be acceptable, criticality analyses were performed to demonstrate that a large number of containers with limiting loadings of fissile material could be stored at the site and meet a k eff limit of 0.95. Criticality analyses based on the classic worst-case moderated plutonium sphere approach would severely limit the capacity for storage of waste at the facility. Therefore, these analyses use realistic or credible worst-case assumptions to better represent the actual storage situation without compromising the margin of safety. Numerous sensitivity studies were performed to determine the importance of various parameters on the criticality of the configuration. It was determined that the plutonium loading has the dominant effect on the system reactivity. Nearly all other reactivity variations from the sensitivity studies were found to be relatively small. The analysis shows that criticality of the contact-handled waste storage drums and boxes and the remote-handled canisters is prevented by restrictions on maximum fissile loading per container and on the size of handling/storage areas
Accident analysis for transuranic waste management alternatives in the U.S. Department of Energy waste management program

International Nuclear Information System (INIS)

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

1995-01-01

Preliminary accident analyses and radiological source term evaluations have been conducted for transuranic waste (TRUW) as part of the US Department of Energy (DOE) effort to manage storage, treatment, and disposal of radioactive wastes at its various sites. The approach to assessing radiological releases from facility accidents was developed in support of the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS). The methodology developed in this work is in accordance with the latest DOE guidelines, which consider the spectrum of possible accident scenarios in the implementation of various actions evaluated in an EIS. The radiological releases from potential risk-dominant accidents in storage and treatment facilities considered in the EM PEIS TRUW alternatives are described in this paper. The results show that significant releases can be predicted for only the most severe and extremely improbable accidents sequences
Radiological hazards of alpha-contaminated waste

International Nuclear Information System (INIS)

Rodgers, J.C.

1982-01-01

The radiological hazards of alpha-contaminated wastes are discussed in this overview in terms of two components of hazard: radiobiological hazard, and radioecological hazard. Radiobiological hazard refers to human uptake of alpha-emitters by inhalation and ingestion, and the resultant dose to critical organs of the body. Radioecological hazard refers to the processes of release from buried wastes, transport in the environment, and translocation to man through the food chain. Besides detailing the sources and magnitude of hazards, this brief review identifies the uncertainties in their estimation, and implications for the regulatory process
Hazardous waste. Annual report, 1984

International Nuclear Information System (INIS)

1985-01-01

Activities in the Hazardous Waste Program area in 1984 ranged from preparing management and long-range plans to arranging training seminars. Past and present generation of hazardous wastes were the key concerns. This report provides a summary of the significant events which took place in 1984. 6 tabs
MANAGEMENT OF TRANSURANIC (TRU) WASTE RETRIEVAL PROJECT RISKS SUCCESSES IN THE STARTUP OF THE HANFORD 200 AREA TRU WASTE RETRIEVAL PROJECT

International Nuclear Information System (INIS)

GREENWLL, R.D.

2005-01-01

A risk identification and mitigation method applied to the Transuranic (TRU) Waste Retrieval Project performed at the Hanford 200 Area burial grounds is described. Retrieval operations are analyzed using process flow diagramming. and the anticipated project contingencies are included in the Authorization Basis and operational plans. Examples of uncertainties assessed include degraded container integrity, bulged drums, unknown containers, and releases to the environment. Identification and mitigation of project risks contributed to the safe retrieval of over 1700 cubic meters of waste without significant work stoppage and below the targeted cost per cubic meter retrieved. This paper will be of interest to managers, project engineers, regulators, and others who are responsible for successful performance of waste retrieval and other projects with high safety and performance risks
Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

International Nuclear Information System (INIS)

Kuan, P.; Bhatt, R.N.

2003-01-01

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-based characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits

Cryofracture as a tool for preprocessing retrieved buried and stored transuranic waste

International Nuclear Information System (INIS)

Loomis, G.G.; Winberg, M.R.; Ancho, M.L.; Osborne, D.

1992-01-01

This paper summarizes important features of an experimental demonstration of applying the Cryofracture process to size-reduce retrieved buried and stored transuranic-contaminated wastes. By size reducing retrieved buried and stored waste, treatment technologies such as thermal treatment can be expedited. Additionally, size reduction of the waste can decrease the amount of storage space required by reducing the volume requirements of storage containers. A demonstration program was performed at the Cryofracture facility by Nuclear Remedial Technologies for the Idaho National Engineering Laboratory. Cryofracture is a size-reducing process whereby objects are frozen to liquid nitrogen temperatures and crushed in a large hydraulic press. Material s at cryogenic temperatures have low ductility and are easily size-reduced by fracturing. Six 55-gallon drums and six 2 x 2 x 8 ft boxes containing simulated waste with tracers were subjected to the Cryofracture process. Data was obtained on (a) cool-down time, (b) yield strength of the containers, (c) size distribution of the waste before and after the Cryofracture process, (d) volume reduction of the waste, and (e) sampling of air and surface dusts for spread of tracers to evaluate potential contamination spread. The Cryofracture process was compared to conventional shredders and detailed cost estimates were established for construction of a Cryofracture facility at the Idaho National Engineering Laboratory
Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1982-08-01

An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables
Pyrometallurgical partitioning of uranium and transuranic elements from rare earth elements by electrorefining and reductive extraction

International Nuclear Information System (INIS)

Uozumi, Koichi; Kinoshita, Kensuke; Inoue, Tadashi; Storvick, T.S.; Krueger, C.L.; Nabelek, C.R.

2001-01-01

High-level liquid waste generated from PUREX reprocessing contains a small amount of transuranic elements, such as Np, Pu, Am, and Cm, with long-lived radioactivities. A pyrometallurgical partitioning process is being developed to recover transuranic elements from such waste. Small amounts of U contained in the high-level liquid waste are also recovered in the process. A key issue for developing the process is effective separation of U and the transuranic elements from the rare-earth elements, because the two elemental groups are chemically analogous. A series of process tests were carried out in the present study to demonstrate that a combination of electrorefining and reductive extraction is useful for separating U and transuranic elements from the rare-earth elements. The results indicate that 99% of U and each transuranic elements is recovered by the combination process as a product, and that the quantity of rare-earth elements contained in the product is smaller than the transuranic elements by weight. The overall mass balance of U and transuranic elements in the system ranged within the experimental errors assigned to sampling and analysis. (author)
Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).
75 FR 11002 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Final Rule

Science.gov (United States)

2010-03-10

... Waste Management System; Identification and Listing of Hazardous Waste; Final Rule AGENCY: Environmental... and specific types of management of the petitioned waste, the quantities of waste generated, and waste... wastes. This final rule responds to a petition submitted by Valero to delist F037 waste. The F037 waste...
Modeling of a dissolution system for transuranic compounds

International Nuclear Information System (INIS)

Chiba, Z.; Dease, C.

1991-02-01

A system is currently being developed at Lawrence Livermore Laboratory to treat transuranic wastes by means of a mediated electrochemical oxidation process. The process involves generating Ag( ++ ) from a solution of silver nitrate and nitric acid in an electrochemical cell. Ag( ++ ) is highly reactive and is capable of attacking many organic and inorganic substances. In particular, if a mixture of particles containing transuranic and other scrap metal oxides is allowed to react with Ag( ++ ) in a nitric acid solution, the transuranic oxides will dissolve and can be removed with the solution leaving the other insoluble oxides behind. The dissolution of the transuranic oxides by reactions with Ag( ++ ) occurs due to further oxidation to higher valence states and the formation of soluble ions such as MO 2 + and MO 2 ++ . 7 refs., 5 figs., 1 tab
Hazardous waste management: Reducing the risk

International Nuclear Information System (INIS)

Goldman, B.A.; Hulme, J.A.; Johnson, C.

1986-01-01

Congress has strengthened the laws under which active hazardous waste facilities are regulated. Nevertheless, after visiting a number of active treatment, storage, and disposal facilities, the Council on Economic Priorities (CEP) found that not only do generators not know which facilities are the best, but that the EPA has not always selected the best facilities to receive wastes removed from Superfund sites. Other facilities were better managed, better located, and better at using more advanced technologies than the facilities the EPA selected. In fact, of the ten facilities CEP evaluated in detail the EPA chose the one that performed worst - CECOS International, Inc. in Williamsburg, Ohio - to receive Superfund wastes in more instances than any of the other nine facilities. Data from a house subcommittee survey indicate that almost half of the operating hazardous waste facilities the EPA chose to receive wastes removed from Superfund sites may have contaminated groundwater. Some of the chosen facilities may even be partially responsible for a share of the wastes they are being paid to clean up. Hazardous waste management strategies and technology, how to evaluate facilities, and case studies of various corporations and hazardous waste management facilities are discussed
Method of estimating maximum VOC concentration in void volume of vented waste drums using limited sampling data: Application in transuranic waste drums

International Nuclear Information System (INIS)

Liekhus, K.J.; Connolly, M.J.

1995-01-01

A test program has been conducted at the Idaho National Engineering Laboratory to demonstrate that the concentration of volatile organic compounds (VOCs) within the innermost layer of confinement in a vented waste drum can be estimated using a model incorporating diffusion and permeation transport principles as well as limited waste drum sampling data. The model consists of a series of material balance equations describing steady-state VOC transport from each distinct void volume in the drum. The primary model input is the measured drum headspace VOC concentration. Model parameters are determined or estimated based on available process knowledge. The model effectiveness in estimating VOC concentration in the headspace of the innermost layer of confinement was examined for vented waste drums containing different waste types and configurations. This paper summarizes the experimental measurements and model predictions in vented transuranic waste drums containing solidified sludges and solid waste
Rapid monitoring for transuranic contaminants during buried waste retrieval

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Shaw, P.G.; Randolph, P.D.; Amaro, C.R.; Pawelko, R.J.; Thompson, D.N.; Loomis, G.G.

1991-03-01

This document reports results of research performed in support of possible future transuranic waste retrieval operations at the Idaho National Engineering Laboratory Radioactive Waste Management Complex. The focus of this research was to evaluate various methods of performing rapid and, as much as possible, ''on-line'' quantitative measurements of 239 Pu or 241 Am, either as airborne or loose contamination. Four different alpha continuous air monitors were evaluated for lower levels of detection of airborne 239 Pu. All of the continuous air monitors were evaluated by sampling ambient air. In addition, three of the continuous air monitors were evaluated by sampling air synthetically laden with clean dust and dust spiked with 239 Pu. Six methods for making quantitative measurements of loose contamination were investigated. They were: (1) microwave digestion followed by counting in a photon electron rejecting alpha liquid scintillation spectrometer, (2) rapid radiochemical separation followed by alpha spectrometry, (3) measurement of the 241 Am 59 keV gamma ray using a thin window germanium detector, (4) measurement of uranium L-shell x-rays, (5) gross alpha counting using a large-area Ag activated ZnS scintillator, and (6) direct counting of alpha particles using a large-area ionization chamber. 40 refs., 42 figs., 24 tabs
The nondestructive assay of 55-gallon drums containing uranium and transuranic waste using passive-active shufflers

International Nuclear Information System (INIS)

Rinard, P.M.; Adams, E.L.; Menlove, H.O.; Sprinkle, J.K. Jr.

1992-11-01

This study has been completed to characterize and improve the performance of passive-active neutron (PAN) shufflers in assaying 55gal. drums of nuclear facility waste for uranium and transuranic elements. Over 1700 active measurements and 800 passive measurements were made using 28 different matrices. Some of the matrices had homogeneous distributions of known amounts of moderating and absorbing materials, whereas others were less well characterized. Some of the well-characterized matrices simulate facility waste better than the others,especially matrices of paper, iron, polyethylene in nine different densities (with and without neutron poisons), alumina trap material, and concrete blocks
Measurements of fission and activation products for Oak Ridge National Laboratory transuranic waste characterization

International Nuclear Information System (INIS)

Nguyen, L.K.; Miller, L.F.; Downing, D.J.

1997-06-01

It is beyond the current nondestructive analysis (NDA) state-of-the-art to accurately measure important alpha- and beta-emitting radionuclides in the presence of typically-occurring background levels of neutron and photon radiation associated with remote handled (RH) transuranic (TRU) waste; in addition, it is not economically feasible to perform destructive analyses (DA) that employ radiochemical techniques on representative random samples from each waste container designated for disposal. Techniques that utilize gamma spectroscopy cannot measure purely alpha-emitting radionuclides, and they are difficult for measurements of photon-emitting radionuclides in large containers with energies below about one hundred keV. The methodology presented in this report combines gamma spectroscopy measurements of waste canisters with radiochemical analyses of smear samples and with statistical analyses to obtain estimates of alpha-emitting radionuclides in waste containers. This approach, with some additional research, is expected to provide an effective and practical technique for characterization of TRU radioactive waste to meet the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) and for segregating waste at the Radiochemical Engineering Development Center (REDC). The objectives of this report are to determine if a waste container generated from ORNL/REDC can be classified as TRU and to provide an appropriate method of estimating the initial TRU concentration in this container
Buried transuranic wastes at ORNL: Review of past estimates and reconciliation with current data

International Nuclear Information System (INIS)

Trabalka, J.R.

1997-09-01

Inventories of buried (generally meaning disposed of) transuranic (TRU) wastes at Oak Ridge National Laboratory (ORNL) have been estimated for site remediation and waste management planning over a period of about two decades. Estimates were required because of inadequate waste characterization and incomplete disposal records. For a variety of reasons, including changing definitions of TRU wastes, differing objectives for the estimates, and poor historical data, the published results have sometimes been in conflict. The purpose of this review was (1) to attempt to explain both the rationale for and differences among the various estimates, and (2) to update the estimates based on more recent information obtained from waste characterization and from evaluations of ORNL waste data bases and historical records. The latter included information obtained from an expert panel's review and reconciliation of inconsistencies in data identified during preparation of the ORNL input for the third revision of the Baseline Inventory Report for the Waste Isolation Pilot Plant. The results summarize current understanding of the relationship between past estimates of buried TRU wastes and provide the most up-to-date information on recorded burials thereafter. The limitations of available information on the latter and thus the need for improved waste characterization are highlighted
Overview of hazardous-waste regulation at federal facilities

International Nuclear Information System (INIS)

Tanzman, E.; LaBrie, B.; Lerner, K.

1982-05-01

This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the federal RCRA requirements on hazardous waste within their borders. Second, Sec. 3 discusses two peculiar provisions of RCRA that appear to permit states to regulate federal facilities more strictly than RCRA otherwise would require
Overview of hazardous-waste regulation at federal facilities

Energy Technology Data Exchange (ETDEWEB)

Tanzman, E.; LaBrie, B.; Lerner, K.

1982-05-01

This report is organized in a fashion that is intended to explain the legal duties imposed on officials responsible for hazardous waste at each stage of its existence. Section 2 describes federal hazardous waste laws, explaining the legal meaning of hazardous waste and the protective measures that are required to be taken by its generators, transporters, and storers. In addition, penalties for violation of the standards are summarized, and a special discussion is presented of so-called imminent hazard provisions for handling hazardous waste that immediately threatens public health and safety. Although the focus of Sec. 2 is on RCRA, which is the principal federal law regulating hazardous waste, other federal statutes are discussed as appropriate. Section 3 covers state regulation of hazardous waste. First, Sec. 3 explains the system of state enforcement of the federal RCRA requirements on hazardous waste within their borders. Second, Sec. 3 discusses two peculiar provisions of RCRA that appear to permit states to regulate federal facilities more strictly than RCRA otherwise would require.
Egyptian Environmental Activities and Regulations for Management of Hazardous Substances and Hazardous Wastes

International Nuclear Information System (INIS)

El Zarka, M.

1999-01-01

A substantial use of hazardous substances is essential to meet the social and economic goals of the community in Egypt. Agrochemicals are being used extensively to increase crop yield. The outdated agrochemicals and their empty containers represent a serious environmental problem. Industrial development in different sectors in Egypt obligates handling of huge amounts of hazardous substances and hazardous wastes. The inappropriate handling of such hazardous substances creates several health and environmental problems. Egypt faces many challenges to control safe handling of such substances and wastes. Several regulations are governing handling of hazardous substances in Egypt. The unified Environmental Law 4 for the year 1994 includes a full chapter on the Management of Hazardous Substances and Hazardous Wastes. National and international activities have been taken to manage hazardous substances and hazardous wastes in an environmental sound manner
40 CFR 262.60 - Imports of hazardous waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Imports of hazardous waste. 262.60 Section 262.60 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE Imports of Hazardous Waste § 262.60 Imports...
30 CFR 47.53 - Alternative for hazardous waste.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Alternative for hazardous waste. 47.53 Section... waste. If the mine produces or uses hazardous waste, the operator must provide potentially exposed miners and designated representatives access to available information for the hazardous waste that— (a...
Risk evaluations of transuranic waste at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Smith, T.H.; Keneshea, F.J.

1980-01-01

Approximately 75% of the defense low-level transuranic (TRU) waste stored in the United States and 25% of the buried TRU waste is located at the Idaho National Engineering Laboratory (INEL). Studies have been performed to identify and evaluate technical alternatives for the long-term management of this waste. (The alternatives range from leaving the waste in place as is to reviewing, processing, and shipping it to an offsite geological repository.) Among the evalations that have been performed were preliminary risk evaluations. The dose commitment and risk of hypothetical, near-term, accidental or uncontrolled releases of radionuclides have been evaluated for each alternative. The following potential causes of radionuclide release have been studied: process and handling accidents, shipping accidents, natural events (e.g., earthquakes), man-caused events (e.g., airplane crashes), and future intrusion by individuals or small populations after loss of societal control over the waste. The hypothetical releases have been evaluated, in terms of dose commitment and (if pertinent) probability and risk, for all operational steps making up each concept. The dominant scanerios in terms of near-term risk are (1) lava flow up through or over the waste, leading to airbone releases; (2) an explosion or a criticality accident in the waste-processing facility; and (3) a tornado strike or a fire during waste retrieval. The dominant long-term releases are (1) volcanic action; and (2) intrusion of people on the waste site.Although substantial dose commitments to individual members of the public were calculated for the lava flow and intrusion scenarios, no prompt health effects would be expected from the exposures. The effects would be in the form of a slightly increased likelihood of latent cancer induction
Waste minimization via destruction of hazardous organics

International Nuclear Information System (INIS)

Austin, L.R.

1991-01-01

Los Alamos National Laboratory is developing technologies that are capable of destroying hazardous organics, that is, converting them basically to water and carbon dioxide. If these technologies were incorporated into the main processing operation where the waste is produced, then the volume and toxicity of the hazardous or mix hazardous waste generated would be significantly reduced. This presentation will briefly discuss some of the waste treatment technologies under development at Los Alamos National Laboratory focused on destroying hazardous organics
Customer service model for waste tracking at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Dorries, Alison M [Los Alamos National Laboratory

2011-02-02

The goal is to transition from five legacy database systems that have reached end-of-life to a single inventory system that supports workflow, data, and reporting for all waste streams. Plutonium Processing Facility (TA-55) Waste Team provides a high quality system that insures safe, efficient and compliant management of all radioactive and hazardous wastes generated, including waste characterization and repackaging of Transuranic Waste (TRU) and TRU mixed waste for shipment to the Waste Isolation Pilot Plant (WIPP).

75 FR 13066 - Hazardous Waste Technical Corrections and Clarifications Rule

Science.gov (United States)

2010-03-18

... hazardous waste and specific types of hazardous waste management facilities, the land disposal restrictions... requirements, the standards for owners and operators of hazardous waste treatment, storage and disposal... hazardous waste management facilities, the land disposal restrictions program, and the hazardous waste...
Household hazardous waste

DEFF Research Database (Denmark)

Fjelsted, Lotte; Christensen, Thomas Højlund

2007-01-01

.) comprised 15-25% and foreign items comprised 10-20%. Water-based paint was the dominant part of the paint waste. The chemical composition of the paint waste and the paint-like waste was characterized by an analysis of 27 substances in seven waste fractions. The content of critical substances was tow......'Paint waste', a part of the 'household hazardous waste', amounting to approximately 5 tonnes was collected from recycling stations in two Danish cities. Sorting and analyses of the waste showed paint waste comprised approximately 65% of the mass, paint-like waste (cleaners, fillers, etc...... and the paint waste was less contaminated with heavy metals than was the ordinary household waste. This may suggest that households no longer need to source-segregate their paint if the household waste is incinerated, since the presence of a small quantity of solvent-based paint will not be harmful when...
Defense Waste Management Plan for buried transuranic-contaminated waste, transuranic-contaminated soil, and difficult-to-certify transuranic waste

International Nuclear Information System (INIS)

1987-06-01

GAO recommended that DOE provide specific plans for permanent disposal of buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; cost estimates for permanent disposal of all TRU waste, including the options for the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; and specific discussions of environmental and safety issues for the permanent disposal of TRU waste. Purpose of this document is to respond to the GAO recommendations by providing plans and cost estimates for the long-term isolation of the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste. This report also provides cost estimates for processing and certifying stored and newly generated TRU waste, decontaminating and decommissioning TRU waste processing facilities, and interim operations
RFID technology for hazardous waste management and tracking.

Science.gov (United States)

Namen, Anderson Amendoeira; Brasil, Felipe da Costa; Abrunhosa, Jorge José Gouveia; Abrunhosa, Glaucia Gomes Silva; Tarré, Ricardo Martinez; Marques, Flávio José Garcia

2014-09-01

The illegal dumping of hazardous waste is one of the most concerning occurrences related to illegal waste activities. The waste management process is quite vulnerable, especially when it comes to assuring the right destination for the delivery of the hazardous waste. The purpose of this paper is to present a new system design and prototype for applying the RFID technology so as to guarantee the correct destination for the hazardous waste delivery. The aim of this innovative approach, compared with other studies that employ the same technology to the waste disposal process, is to focus on the certification that the hazardous waste will be delivered to the right destination site and that no inappropriate disposal will occur in the transportation stage. These studies were carried out based on data collected during visits to two hazardous waste producer companies in Brazil, where the material transportation and delivery to a company in charge of the waste disposal were closely monitored. © The Author(s) 2014.
Hazardous materials and waste management a guide for the professional hazards manager

CERN Document Server

Cheremisinoff, Nicholas P

1995-01-01

The management of hazardous materials and industrial wastes is complex, requiring a high degree of knowledge over very broad technical and legal subject areas. Hazardous wastes and materials are diverse, with compositions and properties that not only vary significantly between industries, but within industries, and indeed within the complexity of single facilities. Proper management not only requires an understanding of the numerous and complex regulations governing hazardous materials and waste streams, but an understanding and knowledge of the treatment, post-treatment, and waste minimizatio
Hazardous-waste analysis plan for LLNL operations

Energy Technology Data Exchange (ETDEWEB)

Roberts, R.S.

1982-02-12

The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste.
Hazardous-waste analysis plan for LLNL operations

International Nuclear Information System (INIS)

Roberts, R.S.

1982-01-01

The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste
Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

International Nuclear Information System (INIS)

Warner, C.L.

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described
Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

Energy Technology Data Exchange (ETDEWEB)

Warner, C.L. (comp.)

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.
Expert geographical information system for assessing hazardous materials in aquatic environments

International Nuclear Information System (INIS)

Regens, J.L.; White, L.; Wright, J.D.; Rene, A.; Mielke, H.; Bakeer, R.; Belkhouche, B.; Barber, M.

1993-01-01

Hazardous substances, including radionuclides, heavy metals, chlorinated hydrocarbons, and industrial solvents, pose unique challenges in terms of environmental restoration and waste management, especially in aquatic environments. When stored, used or disposed of improperly, hazardous materials including transuranic wastes, high level wastes, low level wastes, greater than class C wastes, mixed wastes or chemical wastes can contaminate an array of environmental receptors ranging from soils, sediments, groundwater to surface water. Depending on the specific hazardous substance and site attributes, environmental restoration and waste management can be a complex, problematic activity. This is particularly true for the major Defense Programs facilities managed by the Department of Energy (DOE). This research cluster consists of two discrete elements. Project Element No. 1 develops and applies GIS-based approaches to decision support for environmental restoration by delineating potential exposures and health risks at the Rocky Flats Plant and profiling contemporary and historical demographic/land use patterns at Sandia National Laboratories. Project Element No. 2 develops ESS software for surface water and ground water contaminants in the Mississippi River Basin
HANDBOOK: HAZARDOUS WASTE INCINERATION MEASUREMENT GUIDANCE

Science.gov (United States)

This publication, Volume III of the Hazardous Waste Incineration Guidance Series, contains general guidance to permit writers in reviewing hazardous waste incineration permit applications and trial burn plans. he handbook is a how-to document dealing with how incineration measure...
Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility

International Nuclear Information System (INIS)

Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

1985-03-01

A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed
Hazardous waste shipment data collection from DOE sites

International Nuclear Information System (INIS)

Page, L.A.; Kirkpatrick, T.D.; Stevens, L.

1992-01-01

Past practices at the US Department of Energy (DOE) sites for offsite release of hazardous waste are being reviewed to determine if radioactively contaminated hazardous wastes were released to commercial treatment, storage, and disposal facilities. Records indicating the presence of radioactivity in waste shipped to and treated at a commercial incineration facility led to a ban on offsite hazardous waste shipments and investigation of past practices for offsite release of hazardous waste from the DOE sites. A House of Representatives Interior and Insular Affairs Committee oversight hearing on potentially contaminated waste shipments to commercial facilities concluded that the main issue was the lack of a uniform national standard to govern disposal of mixed waste
Contamination control aspects of attaching waste drums to the WIPP Waste Characterization Chamber

International Nuclear Information System (INIS)

Rubick, L.M.; Burke, L.L.

1998-01-01

Argonne National Laboratory West (ANL-W) is verifying the characterization and repackaging of contact-handled transuranic (CH-TRU) mixed waste in support of the Waste Isolation Pilot Program (WIPP) project located in Carlsbad, New Mexico. The WIPP Waste Characterization Chamber (WCC) was designed to allow opening of transuranic waste drums for this process. The WCC became operational in March of 1994 and has characterized approximately 240 drums of transuranic waste. The waste drums are internally contaminated with high levels of transuranic radionuclides. Attaching and detaching drums to the glove box posed serious contamination control problems. Prior to characterizing waste, several drum attachment techniques and materials were evaluated. An inexpensive HEPA filter molded into the bagging material helps with venting during detachment. The current techniques and procedures used to attach and detach transuranic waste drums to the WCC are described
Proceedings of emerging technologies for hazardous waste management

International Nuclear Information System (INIS)

Tedder, D.W.

1992-01-01

This book contains proceedings of emerging technologies for hazardous waste management. Topics covered include: Low-temperature oxidation of organic chemical wastes; Advanced waste minimization strategies; Treatment of manufactured gas plant (MGP) and similar wastes; Bioremediation of soils and sediments; Advances in radioactive waste treatment; Computer aides approaches to hazardous waste management; Advances in soil remediation; Low-temperature oxidation of organic chemical waste; Boremediation: Micro, meso, and macro-scale processes; In situ remediation techniques; Treatment of hazardous organics with radiation or solar energy; Technologies for management of municipal waste combustion residues; Environmental restoration and waste management; and Advanced separation and stabilization technologies
Study on hazardous substances contained in radioactive waste

International Nuclear Information System (INIS)

Kuroki, Ryoichiro; Takahashi, Kuniaki

2008-01-01

It is necessary that the technical criteria is established concerning waste package for disposal of the TRU waste generated in Japan Atomic Energy Agency. And it is important to consider the criteria not only in terms of radioactivity but also in terms of chemical hazard and criticality. Therefore the environmental impact of hazardous materials and possibility of criticality were investigated to decide on technical specification of radioactive waste packages. The contents and results are as following. (1) Concerning hazardous materials included in TRU waste, regulations on disposal of industrial wastes and on environmental preservation were investigated. (2) The assessment methods for environmental impact of hazardous materials included in radioactive waste in U.K, U.S.A. and France were investigated. (3) The parameters for mass transport assessment about migration of hazardous materials in waste packages around disposal facilities were compiled. And the upper limits of amounts of hazardous materials in waste packages to satisfy the environmental standard were calculated with mass transport assessment for some disposal concepts. (4) It was suggested from criticality analysis for waste packages in disposal facility that the occurrence of criticality was almost impossible under the realistic conditions. (author)
Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

RECHARD,ROBERT P.; SANCHEZ,LAWRENCE C.; STOCKMAN,CHRISTINE T.; TRELLUE,HOLLY R.

2000-04-01

Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low.
Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Rechard, Robert P.; Sanchez, Lawrence C.; Stockman, Christine T.; Trellue, Holly R.

2000-01-01

Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low
Report on the emergency response training and equipment activities through 1991 for the transportation of transuranic waste to the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1992-04-01

The Waste Isolation Pilot Plant (WIPP) is a research and development facility with the mission of demonstrating the safe shipment, emplacement and retrieval of radioactive transuranic (TRU) wastes resulting from the defense activities and programs of the United States. It is the only long-term storage facility constructed for TRU waste. This report provides the status on the Department of Energy (DOE) efforts as of December 31, 1991, regarding emergency response training and equipment funding provided to local, state, and tribal governments for waste shipments to the WIPP. Because of a growing public awareness of transportation activities involving nuclear materials, this report has been prepared to provide a status of the DOE's activities in this regard, as well as the cooperative efforts between the DOE and state and tribal governments
Management feature of transuranic for HTGR and LWR

International Nuclear Information System (INIS)

Wei Jinfeng; Li Fu; Sun Yuliang

2013-01-01

Long-lived actinides from spent fuels can cause potential long-term environ- mental hazards. The generation and incineration of transuranic in different closed fuel cycles were studied. U and Pu were recycled from spent fuel in the 250 MW high-temperature gas-cooled reactor-pebble-bed-module (HTR-PM) U-Pu fuelled core, and then PuO 2 and MOX fuel elements were designed based on this recycled U and Pu. These fuel elements were used to build up a new PuO 2 or MOX fuelled core with the same geometry of the original reactor. Characteristics of transuranic incineration with HTGR open and closed fuel cycles were studied with VSOP code, and the corresponding results from the light water reactor were compared and analyzed. The transuranic generation with HTGR open fuel cycle is almost half of the corresponding result of the light water reactor. Thus, HTGR closed fuel cycles can effectively burn transuranic. (authors)

Exploitation of a Breakthrough in Magnetic Confinement Fusion to Improve Transuranic Incineration

Energy Technology Data Exchange (ETDEWEB)

Schneider, Erich [Nuclear and Radiation Engineering Program, The University of Texas at Austin, Austin, TX 78712 (United States); Kotschenreuther, Mike; Mahajan, Swadesh; Valanju, Prashant [Institute for Fusion Studies, The University of Texas at Austin, Austin, TX 78712 (United States)

2009-06-15

A fusion-assisted transmutation system for the destruction of transuranic nuclear waste is developed by combining a subcritical fusion-fission hybrid assembly uniquely equipped to burn the worst thermal non-fissile transuranic isotopes with a new fuel cycle that uses cheaper light water reactors for most of the transmutation. The centerpiece of this fuel cycle, the high power density compact fusion neutron source (CFNS, 100 MW, outer radius <3 m), is made possible by a new divertor with a heat-handling capacity five times that of the standard alternative. The number of hybrids needed to destroy a given amount of waste is about an order of magnitude below the corresponding number of critical fast spectrum reactors (FR) as the latter cannot fully exploit the new fuel cycle. Also, the time needed for 99% transuranic waste destruction reduces from centuries (with FR) to decades. The generic Hybrid, combining neutron-rich fusion with energy-rich fission, was first conceptualized several decades ago. However, it is only now that accumulated advances in fusion science and technology allow designing a neutron source like CFNS that is simultaneously compact and high power density, offering a neutron source an order of magnitude stronger than that obtained from accelerator driven systems. The former is essential for efficient coupling to the fission blanket, and the latter is key to efficient neutron production necessary to yield high neutron fluxes needed for effective transmutation. The recent invention of the SuperX-Divertor (SXD)1, a new magnetic configuration that allows the system to safely exhaust large heat and particle fluxes peculiar to CFNS-like devices, is a crucial addition to the underlying knowledge base. The subcritical FFTS acquires a definite advantage over the critical FR approach because of its ability to support an innovative fuel cycle that makes the cheaper LWR do the bulk (75%) of the transuranic transmutation via deep burn in an inert matrix fuel
Technical Safety Requirements for the Waste Storage Facilities May 2014

Energy Technology Data Exchange (ETDEWEB)

Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-04-16

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded 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 of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.
Technical Safety Requirements for the Waste Storage Facilities May 2014

International Nuclear Information System (INIS)

Laycak, D. T.

2014-01-01

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded 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 of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.
Documented Safety Analysis for the Waste Storage Facilities March 2010

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2010-03-05

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).
OVERVIEW OF HAZARDOUS/TOXIC WASTE INCINERATION

Science.gov (United States)

Effective hazardous/toxic waste disposal and safe dumpsite cleanup are two of EPA's major missions in the 1980s. Incineration has been recognized as a very efficient process to destroy the hazardous wastes generated by industry or by the dumpsite remediations. The paper provides ...
Hazardous Gas Production by Alpha Particles

International Nuclear Information System (INIS)

LaVerne, Jay A.

2001-01-01

This project focused on the production of hazardous gases in the radiolysis of solid organic matrices, such as polymers and resins, that may be associated with transuranic waste material. Self-radiolysis of radioactive waste is a serious environmental problem because it can lead to a change in the composition of the materials in storage containers and possibly jeopardize their integrity. Experimental determination of gaseous yields is of immediate practical importance in the engineering and maintenance of containers for waste materials. Fundamental knowledge on the radiation chemical processes occurring in these systems allows one to predict outcomes in materials or mixtures not specifically examined, which is a great aid in the management of the variety of waste materials currently overseen by Environmental Management
Resource Conservation and Recovery Act closure plan for the Intermediate-Level Transuranic Storage Facility mixed waste container storage units

International Nuclear Information System (INIS)

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

1992-11-01

This document describes the proposed plan for clean closure of the Intermediate-Level Transuranic Storage Facility mixed waste container storage units at the Idaho National Engineering Laboratory in accordance with the Resource Conservation and Recovery Act closure requirements. Descriptions of the location, size, capacity, history, and current status of the units are included. The units will be closed by removing waste containers in storage, and decontamination structures and equipment that may have contacted waste. Sufficient sampling and documentation of all activities will be performed to demonstrate clean closure. A tentative schedule is provided in the form of a milestone chart
Hazardous waste operational plan for site 300

International Nuclear Information System (INIS)

Roberts, R.S.

1982-01-01

This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department
Solid low-level waste certification strategy

International Nuclear Information System (INIS)

Smith, M.A.

1991-08-01

The purpose of the Solid Low-Level Waste (SLLW) Certification Program is to provide assurance that SLLW generated at the ORNL meets the applicable waste acceptance criteria for those facilities to which the waste is sent for treatment, handling, storage, or disposal. This document describes the strategy to be used for certification of SLLW or ORNL. The SLLW Certification Program applies to all ORNL operations involving the generation, shipment, handling, treatment, storage and disposal of SLLW. Mixed wastes, containing both hazardous and radioactive constituents, and transuranic wastes are not included in the scope of this document. 13 refs., 3 figs
Evaluation of retrieval activities and equipment for removal of containers from the transuranic storage area retrieval enclosure

International Nuclear Information System (INIS)

Bannister, R.; Rhoden, G.; Davies, G.B.

1995-09-01

Since 1970, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory has accepted over 55,000 cubic meters of Transuranic contaminated hazardous waste for interim storage. The waste has been neatly stored in ''cell'' configurations on adjoining, above ground asphalt pads at the Transuranic Storage Area (TSA). A number of reports have been supplied for review and comment describing the methodology and equipment proposed for retrieval of drums and boxes from a storage facility at the INEL site. The contract for this review requires two main issues to be addressed. First, the adequacy of equipment and methodology for the retrieval of containers which have been breached, lost structural integrity, or are otherwise damaged, Second, to review the strategies and equipment for retrieval of intact waste containers. These issues are presented in the following report along with additional detail in the methodology to complete the description of the operations required for retrieval under most operational scenarios. The documentation reviewed is considered to be at an interim stage and is therefore expected to be subject to the development of the methodology from the existing level of detail with input from the facility operators. This review aims to anticipate some of this development by providing suggested detailed methods of retrieval and equipment for both normal and abnormal operations
Plasma destruction of North Carolina's hazardous waste based of hazardous waste generated between the years of 1989 and 1992

International Nuclear Information System (INIS)

Williams, D.L.

1994-01-01

The purpose of this research is to analyze the applicability of the plasma waste destruction technology to North Carolina hazardous waste streams. This study outlines the current regulations, existing technologies, and innovative technologies being considered as hazardous waste treatment alternatives. From this foundation, the study proceeds to identify the superiority of the plasma waste destruction technology. Specific areas of discussion include: temperature capabilities, waste residence time requirements, destruction removal efficiencies, operational efficiencies, economic issues, safety, and maintenance. This study finds the plasma destruction technology to be fully effective and superior to conventional facilities. The technology completely destroys hydrocarbons and can reduce the volume of many other hazardous wastes on the order of one part per million. The required residence time of waste in a plasma facility for effective destruction is a fraction of a second, while the rotary kiln incinerator maintains an average residence time of approximately 5 seconds. Also mass and heat balance calculations are performed to quantify the effectiveness and efficiency of this technology. It is found that one day's average amount of hazardous waste generated in the state of North Carolina can be destroyed in approximately thirty seconds using a standard one megawatt power source. Yet, before this technology is adopted as North Carolina's primary hazardous waste destruction technology, further study is needed so that all issues considered in this research can be conducted in great detail
Regulation and Control of Hazardous Wastes

OpenAIRE

Hans W. Gottinger

1994-01-01

Hazardous waste regulations require disposal in approved dumpsites, where environmental consequences are minimal but entry may be privately very costly. Imperfect policing of regulations makes the socially more costly option illicit disposal preferable form the perspective of the private decision maker. The existence of the waste disposal decision, its economic nature, production independence, and the control over environmental damage are key issues in the economics of hazardous waste managem...
76 FR 59960 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Withdrawal of...

Science.gov (United States)

2011-09-28

... Waste Management System; Identification and Listing of Hazardous Waste; Withdrawal of proposed rule... Permitting Division, Corrective Action and Waste Minimization Section (6PD-C), 1445 Ross Avenue, Dallas, TX... petition. A new petition will be required for this waste stream. List of Subjects in 40 CFR Part 261...
76 FR 5110 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Proposed Rule

Science.gov (United States)

2011-01-28

... will dispose of the leachate at a publicly owned treatment works or at an industrial waste disposal... classification of listed waste pursuant to Sec. Sec. 261.31 and 261.32. Specifically, in its petition, Gulf West... Waste Management System; Identification and Listing of Hazardous Waste; Proposed Rule AGENCY...
Waste management fiscal year 1998 progress report

International Nuclear Information System (INIS)

1998-01-01

The Waste Management Program is pleased to issue the Fiscal Year 1998 Progress Report presenting program highlights and major accomplishments of the last year. This year-end update describes the current initiatives in waste management and the progress DOE has made toward their goals and objectives, including the results of the waste management annual performance commitments. One of the most important program efforts continues to be opening the Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, for the deep geologic disposal of transuranic waste. A major success was achieved this year by the West Valley Demonstration Project in New York, which in June completed the project's production phase of high-level waste processing ahead of schedule and under budget. Another significant accomplishment this year was the award of two privatization contracts for major waste management operations, one at Oak ridge for transuranic waste treatment, and one at Hanford for the Tank Waste Remediation System privatization project. DOE is proud of the progress that has been made, and will continue to pursue program activities that allow it to safely and expeditiously dispose of radioactive and hazardous wastes across the complex, while reducing worker, public, and environmental risks
Hazardous waste management plan, Savannah River Plant

International Nuclear Information System (INIS)

Phifer, M.A.

1984-06-01

All SRP waste storage, disposal, and recycling facilities that have received hazardous waste, low-level radioactive hazardous waste (mixed waste) or process waste since 1980 have been evaluated by EPA standards. Generally the waste storage areas meet all applicable standards. However, additional storage facilities currently estimated at $2 million and waste disposal facilities currently estimated at $20 million will be required for proper management of stored waste. The majority of the disposal facilities are unlined earthen basins that receive hazardous or process wastes and have or have the potential to contaminate groundwater. To come into compliance with the groundwater standards the influents to the basins will be treated or discontinued, the basins will be decommissioned, groundwater monitoring will be conducted, and remedial actions will be taken as necessary. The costs associated with these basin actions are not completely defined and will increase from present estimates. A major cost which has not been resolved is associated with the disposal of the sludge produced from the treatment plants and basin decommissioning. The Low-Level Radioactive Burial Ground which is also a disposal facility has received mixed waste; however, it does not meet the standards for hazardous waste landfills. In order to properly handle mixed wastes additional storage facilities currently estimated at $500,000 will be provided and options for permanent disposal will be investigated
Preliminary fire hazard analysis for the PUTDR and TRU trenches in the Solid Waste Burial Ground

International Nuclear Information System (INIS)

Gaschott, L.J.

1995-01-01

This document represents the Preliminary Fire Hazards Analysis for the Pilot Unvented TRU Drum Retrieval effort and for the Transuranic drum trenches in the low level burial grounds. The FHA was developed in accordance with DOE Order 5480.7A to address major hazards inherent in the facility
Innovative technologies for the remediation of transuranic-contaminated landfills. Appendix 13: USA

International Nuclear Information System (INIS)

Kostelnik, K.

2001-01-01

The Transuranic-Contaminated Arid Landfill Stabilization Programme, formerly the Buried Waste Integrated Demonstration Programme, was organized by the Department of Energy, Office of Technology Development, to (a) manage the development of emerging technologies that could be successfully applied to remediation and (b) promote the use of these technologies to improve environmental restoration and waste management operations for transuranic-contaminated landfills in arid environments. Implementing the Transuranic-Contaminated Arid Landfill Stabilization Programme involved three key strategies: 1) A systems engineering approach was used to include an overall perspective of the entire remediation process; 2) State-of-the-art science and technology were sought for improving the remediation system; 3) Integrated product teams which were comprised of end users, regulators, stakeholders, as well as industry partners were formed
Hazardous Waste Management by healthcare Institutions, Addis ...

African Journals Online (AJOL)

The finding of the study shows that except Zewditu hospital, the rest use proper management to the hazardous waste. Lack of awareness about health hazards of healthcare waste, inadequate training, absence of waste management and disposal systems, insufficient financial and human resources, low priority given to the ...
40 CFR 262.11 - Hazardous waste determination.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Hazardous waste determination. 262.11 Section 262.11 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES... Administrator under 40 CFR 260.21; or (2) Applying knowledge of the hazard characteristic of the waste in light...

Hazardous waste status of discarded electronic cigarettes.

Science.gov (United States)

Krause, Max J; Townsend, Timothy G

2015-05-01

The potential for disposable electronic cigarettes (e-cigarettes) to be classified as hazardous waste was investigated. The Toxicity Characteristic Leaching Procedure (TCLP) was performed on 23 disposable e-cigarettes in a preliminary survey of metal leaching. Based on these results, four e-cigarette products were selected for replicate analysis by TCLP and the California Waste Extraction Test (WET). Lead was measured in leachate as high as 50mg/L by WET and 40mg/L by TCLP. Regulatory thresholds were exceeded by two of 15 products tested in total. Therefore, some e-cigarettes would be toxicity characteristic (TC) hazardous waste but a majority would not. When disposed in the unused form, e-cigarettes containing nicotine juice would be commercial chemical products (CCP) and would, in the United States (US), be considered a listed hazardous waste (P075). While household waste is exempt from hazardous waste regulation, there are many instances in which such waste would be subject to regulation. Manufactures and retailers with unused or expired e-cigarettes or nicotine juice solution would be required to manage these as hazardous waste upon disposal. Current regulations and policies regarding the availability of nicotine-containing e-cigarettes worldwide were reviewed. Despite their small size, disposable e-cigarettes are consumed and discarded much more quickly than typical electronics, which may become a growing concern for waste managers. Copyright © 2015 Elsevier Ltd. All rights reserved.
National Transuranic Program Charter

International Nuclear Information System (INIS)

1994-10-01

The National Transuranic Program Plan and Charter describes the functional elements of the National TRU Program, organizational relationships, programmatic responsibilities, division of work scope among the various DOE organizations that comprise the program, and program baselines against which overall progress will be measured. The charter defines the authorities and responsibilities of various organizations involved in the management of TRU waste throughout the DOE complex
Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.
75 FR 60632 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule

Science.gov (United States)

2010-10-01

... Waste Management System; Identification and Listing of Hazardous Waste; Direct Final Rule AGENCY... management and treatment of several F- and K-waste codes. These waste codes are F037, F038, K048, K049, K051... released from the waste, plausible and specific types of management of the petitioned waste, the quantities...
Hazardous and toxic waste management in Botswana: practices and challenges.

Science.gov (United States)

Mmereki, Daniel; Li, Baizhan; Meng, Liu

2014-12-01

Hazardous and toxic waste is a complex waste category because of its inherent chemical and physical characteristics. It demands for environmentally sound technologies and know-how as well as clean technologies that simultaneously manage and dispose it in an environmentally friendly way. Nevertheless, Botswana lacks a system covering all the critical steps from importation to final disposal or processing of hazardous and toxic waste owing to limited follow-up of the sources and types of hazardous and toxic waste, lack of modern and specialised treatment/disposal facilities, technical know-how, technically skilled manpower, funds and capabilities of local institutions to take lead in waste management. Therefore, because of a lack of an integrated system, there are challenges such as lack of cooperation among all the stakeholders about the safe management of hazardous and toxic waste. Furthermore, Botswana does not have a systematic regulatory framework regarding monitoring and hazardous and toxic waste management. In addition to the absence of a systematic regulatory framework, inadequate public awareness and dissemination of information about hazardous and toxic waste management, slower progress to phase-out persistent and bio-accumulative waste, and lack of reliable and accurate information on hazardous and toxic waste generation, sources and composition have caused critical challenges to effective hazardous and toxic waste management. It is, therefore, important to examine the status of hazardous and toxic waste as a waste stream in Botswana. By default; this mini-review article presents an overview of the current status of hazardous and toxic waste management and introduces the main challenges in hazardous and toxic waste management. Moreover, the article proposes the best applicable strategies to achieve effective hazardous and toxic waste management in the future. © The Author(s) 2014.
Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

Sharples, F.E.; Eyman, L.D.

1987-01-01

Since passage of the 1984 amendments to the Resource Conservation and Recovery Act (RCRA), major changes have occurred in the regulation of hazardous waste. The US Environmental Protection Agency (EPA) has also greatly modified its interpretation of how these regulations apply to wastes from federal facilities, including defense wastes from US Department of Energy (DOE) sites. As a result, the regulatory distinctions between low-level radioactive waste (LLW) and hazardous waste are becoming blurred. This paper discusses recent statutory and regulatory changes and how they might affect the management of LLW at DOE facilities. 6 references
Industrial ecology: Environmental chemistry and hazardous waste

Energy Technology Data Exchange (ETDEWEB)

Manahan, S.E. [Univ. of Missouri, Columbia, MO (United States). Dept. of Chemistry

1999-01-01

Industrial ecology may be a relatively new concept -- yet it`s already proven instrumental for solving a wide variety of problems involving pollution and hazardous waste, especially where available material resources have been limited. By treating industrial systems in a manner that parallels ecological systems in nature, industrial ecology provides a substantial addition to the technologies of environmental chemistry. Stanley E. Manahan, bestselling author of many environmental chemistry books for Lewis Publishers, now examines Industrial Ecology: Environmental Chemistry and Hazardous Waste. His study of this innovative technology uses an overall framework of industrial ecology to cover hazardous wastes from an environmental chemistry perspective. Chapters one to seven focus on how industrial ecology relates to environmental science and technology, with consideration of the anthrosphere as one of five major environmental spheres. Subsequent chapters deal specifically with hazardous substances and hazardous waste, as they relate to industrial ecology and environmental chemistry.
Hazardous waste systems analysis at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Urioste, J.

1997-01-01

Los Alamos National Laboratory produces routine and non-routine hazardous waste as a by-product of mission operations. Hazardous waste commonly generated at the Laboratory includes many types of laboratory research chemicals, solvents, acids, bases, carcinogens, compressed gases, metals, and other solid waste contaminated with hazardous waste. The Los Alamos National Laboratory Environmental Stewardship Office has established a Hazardous Waste Minimization Coordinator to specifically focus on routine and non-routine RCRA, TSCA, and other administratively controlled wastes. In this process, the Waste Minimization Coordinator has developed and implemented a systems approach to define waste streams, estimate waste management costs and develop plans to implement avoidance practices, and develop projects to reduce or eliminate the waste streams at the Laboratory. The paper describes this systems approach
User's manual for remote-handled transuranic waste container welding and inspection fixture

International Nuclear Information System (INIS)

Hauptmann, J.P.

1985-09-01

Rockwell Hanford Operations (Rockwell) has designed built, and tested a prototype remotely operated welding and inspection fixture to be used in making the closure weld on the remote-handled transuranic (RH-TRU) waste container. The RH-TRU waste container has an average TRU concentration in excess of 100 nCi/gm, and a surface radiation dose rate in excess of 200 mrem/h, but not exceeding 100 rem/h. The RH-TRU waste container is to be used by defense waste generator sites in the United States for final packaging of RH-TRU wastes and is compatible with the requirements of the Waste Isolation Pilot Plant (WIPP) and the WIPP handling system. Standard and stacked RH-TRU container designs are available. The standard container is 26 in. in dia. by 121 in. high; the stacked containers are 26 in. in dia. by 61.25 in. high. After loading, two stacked containers are fitted and welded together to form the identical measurements of the standard 121-in. container. The prototype RH-TRU waste container welding and inspection fixture was intended for test and evaluation only, and not for installation in an operating facility. The final RH-TRU waste container welding and inspection fixture drawings (see appendix) incorporate several changes made following operational testing of the original fixture. These modifications are identified in this manual. However, not all modifications have been functionally tested. The purpose of this manual is to aid waste generator sites in designing a remotely operated welding and inspection fixture that will conform to their own requirements. Modifications to the Rockwell design must be evaluated for structural and WIPP handling requirements. This manual also provides design philosophy, component vendor information, and cost estimates
Household hazardous waste management: a review.

Science.gov (United States)

Inglezakis, Vassilis J; Moustakas, Konstantinos

2015-03-01

This paper deals with the waste stream of household hazardous waste (HHW) presenting existing management systems, legislation overview and other relevant quantitative and qualitative information. European Union legislation and international management schemes are summarized and presented in a concise manner by the use of diagrams in order to provide crucial information on HHW. Furthermore, sources and types, numerical figures about generation, collection and relevant management costs are within the scope of the present paper. The review shows that the term used to refer to hazardous waste generated in households is not clearly defined in legislation, while there is absence of specific acts regulating the management of HHW. The lack of obligation to segregate HHW from the household waste and the different terminology used makes it difficult to determine the quantities and composition of this waste stream, while its generation amount is relatively small and, therefore, is commonly overlooked in waste statistics. The paper aims to cover the gap in the related literature on a subject that is included within the crucial waste management challenges at world level, considering that HHW can also have impact on other waste streams by altering the redox conditions or causing direct reactions with other non hazardous waste substances. Copyright © 2014 Elsevier Ltd. All rights reserved.
Overview of Savannah River Plant waste management operations

International Nuclear Information System (INIS)

Haywood, J.E.; Killian, T.H.

1987-01-01

The Du Pont Savannah River Plant (SRP) Waste Management Program is committed to the safe handling, storage, and disposal of wastes that result from the production of special nuclear materials for the US Department of Energy (US DOE). High-level radioactive liquid waste is stored in underground carbon steel tanks with double containment, and the volume is reduced by evaporation. An effluent treatment facility is being constructed to treat low-level liquid hazardous and radioactive waste. Solid low-level waste operations have been improved through the use of engineered low-level trenches, and transuranic waste handling procedures were modified in 1974 to meet new DOE criteria requiring 20-year retrievable storage. An improved disposal technique, Greater Confinement Disposal, is being demonstrated for intermediate-level waste. Nonradioactive hazardous waste is stored on site in RCRA interim status storage buildings. 5 figs
Dismantling of transuranic contaminated facilities

International Nuclear Information System (INIS)

Roux, P.

1985-01-01

The dismantling of transuranic contaminated facilities raises specific problems. A large part of these problems relates to the management of the waste resulting from dismantling. From the experience gained in the different centers CEA and COGEMA it appears that there are industrial solutions in the group CEA and that an engineering company such as SGN can export them [fr
Destruction of hazardous and mixed wastes using mediated electrochemical oxidation in a Ag(II)HNO3 bench scale system

International Nuclear Information System (INIS)

Balazs, B.; Chiba, Z.; Hsu, P.; Lewis, P.; Murguia, L.; Adamson, M.

1997-01-01

Mediated Electrochemical Oxidation (MEO) is a promising technology for the destruction of organic containing wastes and the remediation of mixed wastes containing transuranic components. The combination of a powerful oxidant and an acid solution allows the conversion of nearly all organics, whether present in hazardous or in mixed waste, to carbon dioxide. Insoluble transuranics are dissolved in this process and may be recovered by separation and precipitation.The MEO technique offers several advantages which are inherent in the system. First, the oxidation/dissolution processes are accomplished at near ambient pressures and temperatures (30-70 degrees C). Second, all waste stream components and oxidation products (with the exception of evolved gases) are contained in an aqueous environment. This electrolyte acts as an accumulator for inorganics which were present in the original waste stream, and the large volume of electrolyte provides a thermal buffer for the energy released during oxidation of the organics. Third, the generation of secondary waste is minimal, as the process needs no additional reagents. Finally, the entire process can be shut down by simply turning off the power, affording a level of control unavailable in some other techniques.Numerous groups, both in the United States and Europe, have made substantial progress in the last decade towards understanding the mechanistic pathways, kinetics, and engineering aspects of the process. At Lawrence Livermore National Laboratory, substantial contributions have been made to this knowledge base in these areas and others. Conceptual design and engineering development have been completed for a pilot plant-scale MEO system, and numerous data have been gathered on the efficacy of the process for a wide variety of anticipated waste components. This presentation will review the data collected at LLNL for a bench scale system based primarily on the use of a Ag(II) mediator in a nitric acid electrolyte; results
Disposal of hazardous wastes in Canada's Northwest Territories

International Nuclear Information System (INIS)

Henney, P.L.; Heinke, G.W.

1991-01-01

In the past decade, many jurisdictions have attempted to estimate quantities and types of hazardous wastes generated within their boundaries. Similar studies done in the Northwest Territories (NWT) are out-of-date, incomplete or specific to only one type of waste or geographical location. In 1990, an industry, business and community survey was conducted to determine types and quantities of hazardous wastes generated in the NWT and currently used disposal methods for these wastes. The survey revealed that 2,500 tons of hazardous wastes were generated each year, including waste oil and petroleum products, fuel tank sludges, acid batteries, spent solvents, antifreeze an waste paint. In many regions, disposal of these wastes may be routine, but waste disposal in arctic and subarctic regions presents unique difficulties. Severe climate, transportation expense, isolation and small quantities of waste generated can make standard solutions expensive, difficult or impossible to apply. Unique solutions are needed for northern waste disposal. The aim of this paper is to give an overview of low-cost, on-site or local hazardous wastes disposal options which can be applied in Canada's NWT and also in other arctic, remote or less-developed regions
Development and characterization of basalt-glass ceramics for the immobilization of transuranic wastes

International Nuclear Information System (INIS)

Lokken, R.O.; Chick, L.A.; Thomas, L.E.

1982-09-01

Basalt-based waste forms were developed for the immobilization of transuranic (TRU) contaminated wastes. The specific waste studied is a 3:1 blend of process sludge and incinerator ash. Various amounts of TRU blended waste were melted with Pomona basalt powder. The vitreous products were subjected to a variety of heat treatment conditions to form glass ceramics. The total crystallinity of the glass ceramic, ranging from 20 to 45 wt %, was moderately dependent on composition and heat treatment conditions. Three parent glasses and four glass ceramics with varied composition and heat treatment were produced for detailed phase characterization and leaching. Both parent glasses and glass ceramics were mainly composed of a continuous, glassy matrix phase. This glass matrix entered into solution during leaching in both types of materials. The Fe-Ti rich dispersed glass phase was not significantly degraded by leaching. The glass ceramics, however, exhibited four to ten times less elemental releases during leaching than the parent glasses. The glass ceramic matrix probably contains higher Fe and Na and lower Ca and Mg relative to the parent glass matrix. The crystallization of augite in the glass ceramics is believed to contribute to the improved leach rates. Leach rates of the basalt glass ceramic are compared to those of other TRU nuclear waste forms containing 239 Pu
Trasax '90: An integrated transportation emergency response exercise program involving transuranic waste shipments

International Nuclear Information System (INIS)

Kouba, S.; Everitt, J.

1991-01-01

Over the last five years, the US Department of Energy (DOE), and several states and numerous local governments have been preparing for the transportation of transuranic (TRU) waste to be shipped to the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, near Carlsbad. Seven western states, represented by the Western Governors' Association (WGA), submitted a report to the US Congress that discussed the concerns of their constituents related to the transportation of TRU waste through their communities. One of the three major concerns identified was emergency preparedness. Initial funding to resolve concerns identified in the WGA report to Congress was provided by the US Department of Transportation. Upon receiving funding, lead states were assigned responsibilities to devise programs aimed at increasing public confidence in the areas of most concern. The responsibility for emergency response readiness, as demonstrated through a program of training and responding to simulated accident scenarios, was accepted by the state of Colorado. The state of Colorado laid out an exercise program which expanded upon the DOE training programs already offered to emergency responders along Colorado's designated TRU-waste transportation corridor. The ongoing program included a full-scale field exercise staged in Colorado Springs and dubbed, ''TRANSAX '90.''
Hazardous Waste Remedial Actions Program: integrating waste management

International Nuclear Information System (INIS)

Petty, J.L.; Sharples, F.E.

1986-01-01

The Hazardous Waste Remedial Actions Program was established to integrate Defense Programs' activities in hazardous and mixed waste management. The Program currently provides centralized planning and technical support to the Office of the Assistant Secretary for Defense Programs. More direct project management responsibilities may be assumed in the future. The Program, under the direction of the ASDP's Office of Defense Waste and Transportation Management, interacts with numerous organizational entities of the Department. The Oak Ridge Operations Office has been designated as the Lead Field Office. The Program's four current components cover remedial action project identification and prioritization; technology adaptation; an informative system; and a strategy study for long-term, ''corporate'' project and facility planning
Contact-handled transuranic transportation system structural analysis

International Nuclear Information System (INIS)

Lamoreaux, G.H.; Romesberg, L.E.; Sutherland, S.H.; Duffey, T.A.

1980-01-01

The Transuranic Package Transporter (TRUPACT) is a Type B overpack being developed for contact-handled transuranic waste. End-on, side-on, and corner impacts of the loaded TRUPACT due to a 9 m drop onto an unyielding surface have been analyzed. In each case the analyses progressed from simplified hand approaches to successively more complex finite element calculations. The first analysis of each series represents the hand calculations which were carried out to obtain initial thicknesses of foam. The remaining analyses were performed using the dynamic and nonlinear analysis capabilities of ADINA, a structural analysis finite element computer program
Hazardous and mixed waste transportation program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1993-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas. (J.P.N.)
Hazardous and Mixed Waste Transportation Program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1991-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas

Management, treatment and final disposal of solid hazardous hospital wastes

International Nuclear Information System (INIS)

Sebiani Serrano, T.

2000-01-01

Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency
Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Berreth, P.D.; Fischer, D.K.; Suckel, R.A.

1984-11-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the INEL. The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve handling techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; (c) retrieve, process, and certify the waste for disposal at a federal repository. Fifteen studies are described in this plan for the latter two alternatives. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind water penetration, erosion, and plant and animal intrusion. Several studies proposed will examine special techniques to immobilize or encapsulate the buried waste. Studies of the third alternative will investigate improved retrieval, processing and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies. 19 references, 8 figures, 4 tables
Transmutation of radioactive waste: Effect on the nuclear fuel cycle

International Nuclear Information System (INIS)

Rasmussen, N.C.; Pigford, T.H.

1997-01-01

A committee of the National Research Council reviewed three concepts for transmuting radionuclides recovered from the chemical reprocessing of commercial light-water-reactor (LWR) fuel: LWR transmutation reactors fueled with recycled actinides, advanced liquid-metal reactors (ALMRs), and accelerator-driven subcritical reactors for transmutation of waste (ATW). The concepts were evaluated in terms of: (1) the extent to which waste disposal would benefit from transmutation, (2) time required to reduce the total inventory of radionuclides in the waste and fuel cycle, (3) the complexity of the overall transmutation system, (4) the extent of new development required, and (5) institutional and economic problems of operating such systems. Transmutation could affect geologic disposal of waste by reducing the inventory of transuranics (TRUs), fission products, and other radionuclides in the waste. Reducing the inventory of transuranics does not necessarily affect radiation doses to people who use contaminated ground water if the dissolution rate of transuranics in waste is controlled by elemental solubilities. However, reducing inventories of Am and Pu would decrease potential hazards from human intrusion. The likelihood for underground nuclear criticality would also be reduced. The long-lived fission products Tc-99, I-129, Cs-135 and others typically contribute most to the long-term radiation doses to future populations who use contaminated water from the repository. Their transmutation requires thermal or epithermal neutrons, readily available in LWR and ATW transmutors. ALMR and LWR transmutors would require several hundred years to reduce the total transuranic inventory by even a factor of 10 at constant electric power, and thousands of years for a hundred-fold reduction. For the same electrical power, the ATW could reduce total transuranic inventory about tenfold more rapidly, because of its very high thermal-neutron flux. However, extremely low process losses would be
2013 Los Alamos National Laboratory Hazardous Waste Minimization Report

Energy Technology Data Exchange (ETDEWEB)

Salzman, Sonja L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); English, Charles J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-08-24

Waste minimization and pollution prevention are inherent goals within the operating procedures of Los Alamos National Security, LLC (LANS). The US Department of Energy (DOE) and LANS are required to submit an annual hazardous waste minimization report to the New Mexico Environment Department (NMED) in accordance with the Los Alamos National Laboratory (LANL or the Laboratory) Hazardous Waste Facility Permit. The report was prepared pursuant to the requirements of Section 2.9 of the LANL Hazardous Waste Facility Permit. This report describes the hazardous waste minimization program (a component of the overall Waste Minimization/Pollution Prevention [WMin/PP] Program) administered by the Environmental Stewardship Group (ENV-ES). This report also supports the waste minimization and pollution prevention goals of the Environmental Programs Directorate (EP) organizations that are responsible for implementing remediation activities and describes its programs to incorporate waste reduction practices into remediation activities and procedures. LANS was very successful in fiscal year (FY) 2013 (October 1-September 30) in WMin/PP efforts. Staff funded four projects specifically related to reduction of waste with hazardous constituents, and LANS won four national awards for pollution prevention efforts from the National Nuclear Security Administration (NNSA). In FY13, there was no hazardous, mixedtransuranic (MTRU), or mixed low-level (MLLW) remediation waste generated at the Laboratory. More hazardous waste, MTRU waste, and MLLW was generated in FY13 than in FY12, and the majority of the increase was related to MTRU processing or lab cleanouts. These accomplishments and analysis of the waste streams are discussed in much more detail within this report.
75 FR 51671 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Final Exclusion

Science.gov (United States)

2010-08-23

.... facility produces high-carbon steel tire cord for use in radial tire manufacturing. The steel cord is... delisted waste. Lists of Subjects in 40 CFR Part 261 Environmental protection, Hazardous waste, Recycling...
In situ vitrification applications to hazardous wastes

International Nuclear Information System (INIS)

Liikala, S.

1989-01-01

In Situ Vitrification is a new hazardous waste remediation alternative that should be considered for contaminated soil matrices. According to the authors the advantages of using ISV include: technology demonstrated at field scale; applicable to a wide variety of soils and contaminants; pyrolyzer organics and encapsulates inorganics; product durable over geologic time period; no threat of harm to the public from exposure; and applications available for barrier walls and structural support. The use of ISV on a large scale basis has thus far been limited to the nuclear industry but has tremendous potential for widespread applications to the hazardous waste field. With the ever changing regulations for the disposal of hazardous waste in landfills, and the increasing positive analytical data of ISV, the process will become a powerful source for on-site treatment and hazardous waste management needs in the very near future
Solidification Tests Conducted on Transuranic Mixed Oil Waste (TRUM) at the Rocky Flats Environmental Technology Site (RFETS)

International Nuclear Information System (INIS)

Brunkow, W. G.; Campbell, D.; Geimer, R.; Gilbreath, C.; Rivera, M.

2002-01-01

Rocky Flats Environmental Technology Site (RFETS) near Golden, Colorado is the first major nuclear weapons site within the DOE complex that has been declared a full closure site. RFETS has been given the challenge of closing the site by 2006. Key to meeting this challenge is the removal of all waste from the site followed by site restoration. Crucial to meeting this challenge is Kaiser-Hill's (RFETS Operating Contractor) ability to dispose of significant quantities of ''orphan'' wastes. Orphan wastes are those with no current disposition for treatment or disposal. Once such waste stream, generically referred to as Transuranic oils, poses a significant threat to meeting the closure schedule. Historically, this waste stream, which consist of a variety of oil contaminated with a range of organic solvents were treated by simply mixing with Environstone. This treatment method rendered a solidified waste form, but unfortunately not a TRUPACT-II transportable waste. So for the last ten years, RFETS has been accumulating these TRU oils while searching for a non-controversial treatment option
Hazardous waste and environmental trade: China`s issues

Energy Technology Data Exchange (ETDEWEB)

Ma Jiang [National Research Center for Science and Technology for Development, Beijing (China)

1996-12-31

By presenting some case studies, this paper analyzes China`s situation with regard to hazardous waste: its environmental trade, treatment, and management. The paper describes China`s experiences with the environmental trade of hazardous waste in both the internal and international market. Regulations for managing the import of waste are discussed, as are China`s major approaches to the trading of hazardous waste both at home and overseas. The major reasons for setting up the Asian-Pacific Regional Training Center for Technology Transfer and Environmental Sound Management of Wastes in China and the activities involved in this effort are also described. 1 tab.
RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

International Nuclear Information System (INIS)

KOZLOWSKI, S.D.

2007-01-01

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below
EXAMPLE OF A RISK-BASED DISPOSAL APPROVAL: SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

International Nuclear Information System (INIS)

PRIGNANO AL

2007-01-01

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

International Nuclear Information System (INIS)

Ryan, E.M.

1995-05-01

This paper will discuss the value of assessments in Lawrence Livermore National Laboratory's Waste Certification Programs by: introducing the organization and purpose of the LLNL Waste Certification Programs for transuranic, low-level, and hazardous waste; examining the differences in internal assessment/audit requirements for these programs; discussing the values and costs of assessments in a waste certification program; presenting practical recommendations to maximize the value of your assessment programs; and presenting improvements in LLNL's waste certification processes that resulted from assessments
Conceptual design of retrieval systems for emplaced transuranic waste containers in a salt bed depository. Final report

International Nuclear Information System (INIS)

Fogleman, S.F.

1980-04-01

The US Department of Energy and the Nuclear Regulatory Commission have jurisdiction over the nuclear waste management program. Design studies were previously made of proposed repository site configurations for the receiving, processing, and storage of nuclear wastes. However, these studies did not provide operational designs that were suitable for highly reliable TRU retrieval in the deep geologic salt environment for the required 60-year period. The purpose of this report is to develop a conceptual design of a baseline retrieval system for emplaced transuranic waste containers in a salt bed depository. The conceptual design is to serve as a working model for the analysis of the performance available from the current state-of-the-art equipment and systems. Suggested regulations would be based upon the results of the performance analyses
Hazardous healthcare waste management in the Kingdom of Bahrain

International Nuclear Information System (INIS)

Mohamed, L.F.; Ebrahim, S.A.; Al-Thukair, A.A.

2009-01-01

Hazardous healthcare waste has become an environmental concern for many developing countries including the Kingdom of Bahrain. There have been several significant obstacles facing the Kingdom in dealing with this issue including; limited documentation regarding generation, handling, management, and disposal of waste. This in turn hinders efforts to plan better healthcare waste management. In this paper, hazardous waste management status in the Kingdom has been investigated through an extensive survey carried out on selected public and private healthcare premises. Hazardous waste management practices including: waste generation, segregation, storage, collection, transportation, treatment, and disposal were determined. The results of this study along with key findings are discussed and summarized. In addition; several effective recommendations and improvements of hazardous waste management are suggested.
Hazards from radioactive waste in perspective

International Nuclear Information System (INIS)

Cohen, B.L.

1979-01-01

This paper compares the hazards from wastes from a 1000-MW(e) nuclear power plant to these from wastes from a 1000-MW(e) coal fueled power plant. The latter hazard is much greater than the former. The toxicity and carcinogenity of the chemicals prodcued in coal burning is emphasized. Comparisions are also made with other toxic chemicals and with natural radioactivity
Automated economic analysis model for hazardous waste minimization

International Nuclear Information System (INIS)

Dharmavaram, S.; Mount, J.B.; Donahue, B.A.

1990-01-01

The US Army has established a policy of achieving a 50 percent reduction in hazardous waste generation by the end of 1992. To assist the Army in reaching this goal, the Environmental Division of the US Army Construction Engineering Research Laboratory (USACERL) designed the Economic Analysis Model for Hazardous Waste Minimization (EAHWM). The EAHWM was designed to allow the user to evaluate the life cycle costs for various techniques used in hazardous waste minimization and to compare them to the life cycle costs of current operating practices. The program was developed in C language on an IBM compatible PC and is consistent with other pertinent models for performing economic analyses. The potential hierarchical minimization categories used in EAHWM include source reduction, recovery and/or reuse, and treatment. Although treatment is no longer an acceptable minimization option, its use is widespread and has therefore been addressed in the model. The model allows for economic analysis for minimization of the Army's six most important hazardous waste streams. These include, solvents, paint stripping wastes, metal plating wastes, industrial waste-sludges, used oils, and batteries and battery electrolytes. The EAHWM also includes a general application which can be used to calculate and compare the life cycle costs for minimization alternatives of any waste stream, hazardous or non-hazardous. The EAHWM has been fully tested and implemented in more than 60 Army installations in the United States
Activities in department of energy hazardous and mixed waste defense waste management

International Nuclear Information System (INIS)

Eyman, L.D.

1988-01-01

In January 1986, the U.S. Department of Energy (DOE) Office of Assistant Secretary for Defense Programs (DP) created the Hazardous Waste and Remedial Actions Division within the Office of Defense Waste and Transportation Management. The Oak Ridge Operations Office (ORO) was assigned the responsibility for supporting DOE Headquarters (HQ) in planning nationally integrated activities for Resource Conservation and Recovery Act/Comprehensive Environmental Response, Compensation, and Liability Act/Superfund Amendments and Reauthorization Act (RCRA/CERCLA/SARA) compliance. In turn, ORO created the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAPSCO) to assist with the expanded lead assignment. The HAZWRAPSCO activities are currently supported by three distinct DOE-HQ funding elements: the Environmental Restoration Program, the Hazardous Waste Compliance Technology Program, and the Hazardous Waste Research and Development R and D Program. The Environmental Restoration Program is discussed in the paper, entitled The DOE Defense Program for Environmental Restoration
High-level waste description, inventory and hazard

International Nuclear Information System (INIS)

Crandall, J.; Hennelly, E.J.; McElroy, J.L.

1983-01-01

High-level nuclear waste (HLW), including its origin, is described and the current differences in definitions discussed. Quantities of defense and commercial radioactive HLW, both volume and curie content, are given. Current waste handling, which is interimin nature, is described for the several sites. The HLW hazard is defined by the times during which various radionuclides are the dominant contributors. The hazard is also compared to that of the ore. Using ICRP-2, which is the legal reference in the US, the hazard of the waste reduces to a level equal to the ore in about 300 years. The disposal plans are summarized and it is shown that regulatory requirements will probably govern disposal operations in such a conservative manner that the risk (product of hazard times probability of release) may well be lower than for any other wastes in existence or perhaps lower than those for any other human endeavor
Innovative technologies for the treatment of hazardous and mixed wastes

International Nuclear Information System (INIS)

Eyman, L.D.; Anderson, T.D.

1988-01-01

The treatment, storage, and disposal of hazardous and mixed wastes incur significant costs for Department of Energy (DOE) installations. These wastes must be managed under strict environmental controls and regulations to prevent the possibility of migration of hazardous materials to the biosphere. Through the Hazardous Waste Remedial Actions Program, the DOE is seeking to develop innovative ways of improving current treatment technologies to eliminate the hazardous components of wastes, reduce waste management costs, and minimize the volume requiring disposal as hazardous or mixed waste. Sponsored projects progress from research and development to field demonstration. Among the innovative technologies under development are supercritical water oxidation of hazardous chemicals, microwave-assisted destruction of chlorinated hydrocarbons, paramagnetic separation of metals from waste, detoxification and reclamation of waste acid, nitrate destruction through calcination, treatment/disposal of reactive metals, and methodologies for encapsulation. Technologies at a demonstration phase include detoxification of mixed waste sludge, microbial degradation of polychlorinated biphenyls in soil, and the remediation process for a hydrocarbon spill. 14 refs
Radiotoxic hazard measure for buried solid radioactive waste

International Nuclear Information System (INIS)

Hamstra, J.

1975-01-01

The radiotoxic hazards resulting from the disposal of highlevel reprocessing wastes into a deep geological formation are reviewed. The term radiotoxic hazard measure (RHM), used to measure the hazard from buried radioactive wastes, is based on the maximum radionuclide concentration permissible in water. Calculations are made of the RHM levels for the high-level reprocessing wastes of both light-water-reactor and fast breeder reactor fuels. In comparing these RHM levels with that for the natural activity of an equivalent amount of uranium ore and its mill tailings, it is concluded that an actual additional radiotoxic hazard for buried high-level reprocessing waste only exists for the first 300 to 500 years after burial. (U.S.)
TSA waste stream and final waste form composition

International Nuclear Information System (INIS)

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

1993-01-01

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

Hazardous waste research and development in the Pacific Basin

International Nuclear Information System (INIS)

Cirillo, R.R.; Carpenter, R.A.

1989-01-01

The effective management of hazardous waste is an issue that all countries of the Pacific Basin must address. By very rough estimates, almost 272 million metric tons of hazardous wastes are being generated every year in the region. While the data are not consistently defined and reported, they do indicate the extent of the problem. Increasing development brings along an increase in the rate of hazardous waste generation. On this basis, the developing countries of the region can be expected to experience some of the same problems of the developed countries as their economies become more industrialized. Fundamental problems are involved in the compilation of consistent hazardous-waste generation statistics in the Pacific Basin. One involves the definition of what constitutes hazardous waste
COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE

International Nuclear Information System (INIS)

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

2003-01-01

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance
Direct conversion of plutonium metal, scrap, residue, and transuranic waste to glass

International Nuclear Information System (INIS)

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.; Malling, J.F.; Rudolph, J.

1995-01-01

A method for the direct conversion of metals, ceramics, organics, and amorphous solids to borosilicate glass has been invented. The process is called the Glass Material Oxidation and Dissolution System (GMODS). Traditional glass-making processes can convert only oxide materials to glass. However, many wastes contain complex mixtures of metals, ceramics, organics, and amorphous solids. Conversion of such mixtures to oxides followed by their conversion to glass is often impractical. GMODS may create a practical method to convert such mixtures to glass. Plutonium-containing materials (PCMS) exist in many forms, including metals, ceramics, organics, amorphous solids, and mixtures thereof. These PCMs vary from plutonium metal to filters made of metal, organic binders, and glass fibers. For storage and/or disposal of PCMS, it is desirable to convert PCMs to borosilicate glass. Borosilicate glass is the preferred repository waste form for high-level waste (HLW) because of its properties. PCMs converted to a transuranic borosilicate homogeneous glass would easily pass all waste acceptance and storage criteria. Conversion of PCMs to a glass would also simplify safeguards by conversion of heterogeneous PCMs to homogeneous glass. Thermodynamic calculations and proof-of-principle experiments on the GMODS process with cerium (plutonium surrogate), uranium, stainless steel, aluminum, Zircaloy-2, and carbon were successfully conducted. Initial analysis has identified potential flowsheets and equipment. Major unknowns remain, but the preliminary data suggests that GMODS may be a major new treatment option for PCMs
Universal requisition for waste data collection

Energy Technology Data Exchange (ETDEWEB)

Nisbet, B.; Gage, M.

1995-05-01

Lawrence Livermore National Laboratory (LLNL) has developed a data management tool for information gathering that encompasses all types of waste generated by the site. It is referred to as the Universal Requisition. It can be used to record information for the following types of waste: non-hazardous, hazardous, low level radioactive, mixed, transuranic (TRU), and TRU mixed wastestreams. It provides the salient information needed for the safe handling, storage, and disposal of waste, and satisfies our regulatory, record keeping, and reporting requirements. There are forty two numbered fields on the requisition and several other fields for signatures, compatibility codes, internal tracking numbers, and other information. Not all of these fields are applicable to every type of waste. As an aid to using the Universal requisition, templates with the applicable fields highlighted in color were produced and distributed. There are six different waste type templates. Each is highlighted in a different color.
Environmentally sound management of hazardous waste and hazardous recyclable materials

International Nuclear Information System (INIS)

Smyth, T.

2002-01-01

Environmentally sound management or ESM has been defined under the Basel Convention as 'taking all practicable steps to ensure that hazardous wastes and other wastes are managed in a manner which will protect human health and the environment against the adverse effects which may result from such wastes'. An initiative is underway to develop and implement a Canadian Environmentally Sound Management (ESM) regime for both hazardous wastes and hazardous recyclable materials. This ESM regime aims to assure equivalent minimum environmental protection across Canada while respecting regional differences. Cooperation and coordination between the federal government, provinces and territories is essential to the development and implementation of ESM systems since waste management is a shared jurisdiction in Canada. Federally, CEPA 1999 provides an opportunity to improve Environment Canada's ability to ensure that all exports and imports are managed in an environmentally sound manner. CEPA 1999 enabled Environment Canada to establish criteria for environmentally sound management (ESM) that can be applied by importers and exporters in seeking to ensure that wastes and recyclable materials they import or export will be treated in an environmentally sound manner. The ESM regime would include the development of ESM principles, criteria and guidelines relevant to Canada and a procedure for evaluating ESM. It would be developed in full consultation with stakeholders. The timeline for the development and implementation of the ESM regime is anticipated by about 2006. (author)
Vitrification of hazardous and mixed wastes

International Nuclear Information System (INIS)

Jantzen, C.M.; Pickett, J.B.; Ramsey, W.G.

1992-01-01

Solidification of hazardous/mixed wastes into glass is being examined at the Savannah River Site. The first hazardous/mixed wastes glassified at SRS have been (1) incinerator and (2) nickel plating line (F006) wastes. Solidification of incinerator blowdown and mixtures of incinerator blowdown and incinerator bottom kiln ash have been achieved in Soda (Na 2 O) - Lime (CaO) - Silica (SiO 2 ) glass (SLS) at waste loadings of up to 50 wt%. Solidification of nickel-plating line waste sludges containing depleted uranium have also been achieved in both SLS and borosilicate glasses at waste loadings of 75 wt%. This corresponds to volume reductions of 97% and 81%, respectively. Further studies will examine glassification of: ion exchange zeolites, inorganic filter media, asbestos, glass fiber filters, contaminated soil, cementitious, or other materials in need of remediation
Automation of ORIGEN2 calculations for the transuranic waste baseline inventory database using a pre-processor and a post-processor

International Nuclear Information System (INIS)

Liscum-Powell, J.

1997-06-01

The purpose of the work described in this report was to automate ORIGEN2 calculations for the Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Database (WTWBID); this was done by developing a pre-processor to generate ORIGEN2 input files from WWBID inventory files and a post-processor to remove excess information from the ORIGEN2 output files. The calculations performed with ORIGEN2 estimate the radioactive decay and buildup of various radionuclides in the waste streams identified in the WTWBID. The resulting radionuclide inventories are needed for performance assessment calculations for the WIPP site. The work resulted in the development of PreORG, which requires interaction with the user to generate ORIGEN2 input files on a site-by-site basis, and PostORG, which processes ORIGEN2 output into more manageable files. Both programs are written in the FORTRAN 77 computer language. After running PreORG, the user will run ORIGEN2 to generate the desired data; upon completion of ORIGEN2 calculations, the user can run PostORG to process the output to make it more manageable. All the programs run on a 386 PC or higher with a math co-processor or a computer platform running under VMS operating system. The pre- and post-processors for ORIGEN2 were generated for use with Rev. 1 data of the WTWBID and can also be used with Rev. 2 and 3 data of the TWBID (Transuranic Waste Baseline Inventory Database)
T-Rex system for operation in TRU, LLW, and hazardous zones

International Nuclear Information System (INIS)

Kline, H.M.; Andreychek, T.P.; Beeson, B.K.

1993-01-01

There are a large number of sites around the world containing TRU (transuranic) waste, low level waste (LLW), and hazardous areas that require teleoperated, heavy lift manipulators with long reach and high precision to handle the materials stored there. Teleoperation of the equipment is required to reduce the risk to operating personnel to as-low-as-reasonably-achievable (ALARA) levels. The Transuranic Storage Area Remote Excavator system (T-Rex) is designed to fill this requirement at low cost through the integration of a production front shovel excavator with a control system, local and remote operator control stations, a closed-circuit television system (CCTV), multiple end effectors and a quick-change system. This paper describes the conversion of an off-the-shelf excavator with a hydraulic control system, the integration of an onboard remote control system, vision system, and the design of a remote control station
EG and G long-range hazardous waste program plan

International Nuclear Information System (INIS)

1985-02-01

The purpose of this document is to develop and implement a program for safe, economic management of hazardous and radioactive mixed waste generated, transported, treated, stored, or disposed of by EG and G Idaho operated facilities. The initial part of this program involves identification and characterization of EG and G-generated hazardous and radioactive mixed waste, and activities for corrective action, including handling, packaging, and shipping of these wastes off site for treatment, storage, and/or disposal, or for interim remedial action. The documentation necessary for all areas of the plan is carefully defined, so as to ensure compliance, at every step, with the requisite orders and guidelines. A second part of this program calls for assessment, and possible development and implementation of a treatment, storage, and disposal (T/S/D) program for special hazardous and radioactive mixed wastes which cannot practically, economically, and safely be disposed of at off-site facilities. This segment of the plan addresses obtaining permits for the existing Waste Experimental Reduction Facility (WERF) incinerator and for the construction of an adjacent hazardous waste solidification facility and a storage area. The permitting and construction of a special hazardous waste treatment and storage facility is also explored. The report investigates permitting the Hazardous Waste Storage Facility (HWSF) as a permanent storage facility
Combined transuranic-strontium extraction process

Science.gov (United States)

Horwitz, E. Philip; Dietz, Mark L.

1992-01-01

The transuranic (TRU) elements neptunium, plutonium and americium can be separated together with strontium from nitric acid waste solutions in a single process. An extractant solution of a crown ether and an alkyl(phenyl)-N,N-dialkylcarbanylmethylphosphine oxide in an appropriate diluent will extract the TRU's together with strontium, uranium and technetium. The TRU's and the strontium can then be selectively stripped from the extractant for disposal.
Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.
Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions
High temperature slagging incineration of hazardous waste

International Nuclear Information System (INIS)

Vanbrabant, R.; Van de Voorde, N.

1987-01-01

The SCK/CEN, as the treatment center for the low level radioactive waste in Belgium, develops appropriate treatment systems for different kinds of wastes. The technical concept of the high temperature slagging incineration system has been developed and improved. The construction of the first demonstration plant was initiated in 1974. Since then the system has been operated regularly and further developed with the view to industrial operations. Now it handles about 5 tons of waste in a week. The waste which is treated consists of low level beta/gamma and alpha-contaminated radioactive waste. Because of the special characteristics the system is thought to be an excellent incineration system for industrial hazardous waste as well. Recently the SCK/CEN has received the authorization to treat industrial hazardous waste in the same installation. Preliminary tests have been executed on special waste products, such as PCB-contaminated liquids, with excellent incineration results. Incineration efficiency up to 99.9999% could be obtained. The paper presents the state of the art of this original The SCK/CEN-technology and gives the results of the tests done with special hazard
Potential problems from shipment of high-curie content contact-handled transuranic (CH-TRU) waste to WIPP

International Nuclear Information System (INIS)

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

1983-08-01

There are about 1000 drums of contact-handled transuranic (CH-TRU) wastes containing more than 100 Ci/drum of Pu-238 that are stored at the Savannah River Plant and at the Los Alamos National Laboratory. Studies performed at DOE laboratories have shown that large quantities of gases are generated in stored drums containing 100 Ci of 238 Pu. Concentrations of hydrogen gas in the void space of the drums are often found to be high enough to be explosive. None of the analyses in the DOE WIPP Final Environmental Impact Statement, Safety Analysis Report, and Preliminary Transportation Analysis have considered the possibility that the generation of hydrogen gas by radiolysis may create an explosive or flammable hazard that could increase the frequency and severity of accidental releases of radionuclides during transportation or handling. These high 238 Pu concentration containers would also increase the estimated doses received by individuals and populations from transportation, WIPP site operations, and human intrusion scenarios even if the possibility of gas-enhanced releases is ignored. The WIPP Project Office has evaluated this effect on WIPP site operations and is suggesting a maximum limit of 140 239 Pu equivalent curies (P-Ci) per drum so that postulated accidental off-site doses will not be larger than those listed in the FEIS. The TRUPACT container, which is being designed for the transportation of CH-TRU wastes to WIPP, does not appear to meet the Nuclear Regulatory Commission regulations requiring double containment for the transportation of plutonium in quantities >20 Ci. A 20 alpha Ci/shipment limit would require about 200,000 shipments for the 4 million curies of alpha emitters slated for WIPP
Hazard ranking systems for chemical wastes and chemical waste sites

International Nuclear Information System (INIS)

Waters, R.D.; Parker, F.L.; Crutcher, M.R.

1991-01-01

Hazardous materials and substances have always existed in the environment. Mankind has evolved to live with some degree of exposure to toxic materials. Until recently the risk has been from natural toxins or natural background radiation. While rapid technological advances over the past few decades have improved the lifestyle of our society, they have also dramatically increased the availability, volume and types of synthetic and natural hazardous materials. Many of their effects are as yet uncertain. Products and manufacturing by-products that no longer serve a useful purpose are deemed wastes. For some waste products land disposal will always be their ultimate fate. Hazardous substances are often included in the waste products. One needs to classify wastes by degree of hazard (risk). Risk (degree of probability of loss) is usually defined for risk assessment as probability of an occurrence times the consequences of the occurrence. Perhaps even more important than the definition of risk is the choice of a risk management strategy. The choice of strategy will be strongly influenced by the decision criteria used. Those decision criteria could be utility (the greatest happiness of the greatest number), rights or technology based or some combination of the three. It is necessary to make such choices about the definition of risks and criteria for management. It is clear that these are social (i.e., political) and value choices and science has little to say on this matter. This is another example of what Alvin Weinberg has named Transcience where the subject matter is scientific and technical but the choices are social, political and moral. This paper shall deal only with the scientific and technical aspects of the hazardous waste problem to create a hazardous substances classification system
Brief summary of slag handling options reviewed for the slagging pyrolysis incinerator in the transuranic waste treatment facility (TWIF) at the INEL

International Nuclear Information System (INIS)

Darnell, G.R.

1980-06-01

This report summarizes the technical problems associated with molten transuranic waste slag as it flows from the incinerator shaft (gasifier) of the slagging pyrolysis incinerator. It addresses essential gasifier seals, slag casting and pouring technology, and transportation and packaging problems. Areas requiring further study and testing are identified
Transuranic radionuclides in the environment surrounding radioactive waste diposal sites, a bibliography

International Nuclear Information System (INIS)

Stoker, A.C.; Noshkin, V.E.; Wong, K.M.; Brunk, J.L.; Conrado, C.L.; Jones, H.E.; Kehl, S.; Stuart, M.L.; Wasley, L.M.; Bradsher, R.V.

1994-08-01

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e. site specific). An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. In an attempt to gather relevant information about the transuranic radionuclides in a variety of environments, we conducted an extensive literature search. In our literature search we identified over 5700 potential written sources of information for review. In addition, we have identified many references which were not found through the literature searches, but which were known to contain useful data. A total of approximately 2600 documents were determined to contain information which would be useful for an in depth study of radionuclides in different environments. The journal articles, books, reports and other documents were reviewed to obtain the source term of the radionuclides studied. Most references containing laboratory study data were not included in our databases. Although these may contain valuable data, we were trying to compile references with information on the behavior of the transuranics in the specific environment being studied
Regulatory barriers to hazardous waste technology innovation

International Nuclear Information System (INIS)

Kuusinen, T.L.; Siegel, M.R.

1991-02-01

The primary federal regulatory programs that influence the development of new technology for hazardous waste are the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA, also commonly known as Superfund). Two important aspects of RCRA that can create barriers to hazardous waste technology innovation are technology-based waste pre-treatment standards and a cumbersome permitting program. By choosing a technology-based approach to the RCRA land disposal restrictions program, the US Environmental Protection Agency (EPA) has simultaneously created tremendous demand for the technologies specified in its regulations, while at the same time significantly reduced incentives for technology innovation that might have otherwise existed. Also, the RCRA hazardous waste permitting process can take years and cost hundreds of thousands of dollars. The natural tendency of permit writers to be cautious of unproven (i.e., innovative) technology also can create a barrier to deployment of new technologies. EPA has created several permitting innovations, however, to attempt to mitigate this latter barrier. Understanding the constraints of these permitting innovations can be important to the success of hazardous waste technology development programs. 3 refs
75 FR 62040 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Proposed Exclusion

Science.gov (United States)

2010-10-07

... the lists of hazardous waste listed at 40 CFR 261.31, both past and currently generated sludge... water production waste treatment system. Once- through non-contact cooling water does not require... grease, sulfide, water content, corrosivity and ignitability. The sludge characterization included...
Performance assessment requirements for the identification and tracking of transuranic waste intended for disposal at the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Snider, C.A. [Department of Energy, Carlsbad, NM (United States); Weston, W.W. [Westinghouse Electric Corp., Carlsbad, NM (United States)

1997-11-01

To demonstrate compliance with environmental radiation protection standards for management and disposal of transuranic (TRU) radioactive wastes, a performance assessment (PA) of the Waste Isolation Pilot Plant (WIPP) was made of waste-waste and waste-repository interactions and impacts on disposal system performance. An estimate of waste components and accumulated quantities was derived from a roll-up of the generator/storage sites` TRU waste inventories. Waste components of significance, and some of negligible effect, were fixed input parameters in the model. The results identified several waste components that require identification and tracking of quantities to ensure that repository limits are not exceeded. The rationale used to establish waste component limits based on input estimates is discussed. The distinction between repository limits and waste container limits is explained. Controls used to ensure that no limits are exceeded are identified. For waste components with no explicit repository based limits, other applicable limits are contained in the WIPP Waste Acceptance Criteria (WAC). The 10 radionuclides targeted for identification and tracking on either a waste container or a waste stream basis include Am-241, Pu-238, Pu-239, Pu-240, Pu-242, U-233, U-234, U-238, Sr-90, and Cs-137. The accumulative activities of these radionuclides are to be inventoried at the time of emplacement in the WIPP. Changes in inventory curie content as a function of radionuclide decay and ingrowth over time will be calculated and tracked. Due to the large margin of compliance demonstrated by PA with the 10,000 year release limits specified, the quality assurance objective for radioassay of the 10 radionuclides need to be no more restrictive than those already identified for addressing the requirements imposed by transportation and WIPP disposal operations in Section 9 of the TRU Waste Characterization Quality Assurance Program Plan. 6 refs.

Integrating Total Quality Management (TQM) and hazardous waste management

Energy Technology Data Exchange (ETDEWEB)

Kirk, Nancy [Colorado State Univ., Fort Collins, CO (United States)

1993-11-01

The Resource Conservation and Recovery Act (RCRA) of 1976 and its subsequent amendments have had a dramatic impact on hazardous waste management for business and industry. The complexity of this law and the penalties for noncompliance have made it one of the most challenging regulatory programs undertaken by the Environmental Protection Agency (EPA). The fundamentals of RCRA include ``cradle to grave`` management of hazardous waste, covering generators, transporters, and treatment, storage, and disposal facilities. The regulations also address extensive definitions and listing/identification mechanisms for hazardous waste along with a tracking system. Treatment is favored over disposal and emphasis is on ``front-end`` treatment such as waste minimization and pollution prevention. A study of large corporations such as Xerox, 3M, and Dow Chemical, as well as the public sector, has shown that well known and successful hazardous waste management programs emphasize pollution prevention and employment of techniques such as proactive environmental management, environmentally conscious manufacturing, and source reduction. Nearly all successful hazardous waste programs include some aspects of Total Quality Management, which begins with a strong commitment from top management. Hazardous waste management at the Rocky Flats Plant is further complicated by the dominance of ``mixed waste`` at the facility. The mixed waste stems from the original mission of the facility, which was production of nuclear weapons components for the Department of Energy (DOE). A Quality Assurance Program based on the criterion in DOE Order 5700.6C has been implemented at Rocky Flats. All of the elements of the Quality Assurance Program play a role in hazardous waste management. Perhaps one of the biggest waste management problems facing the Rocky Flats Plant is cleaning up contamination from a forty year mission which focused on production of nuclear weapon components.
Integrating Total Quality Management (TQM) and hazardous waste management

International Nuclear Information System (INIS)

Kirk, N.

1993-01-01

The Resource Conservation and Recovery Act (RCRA) of 1976 and its subsequent amendments have had a dramatic impact on hazardous waste management for business and industry. The complexity of this law and the penalties for noncompliance have made it one of the most challenging regulatory programs undertaken by the Environmental Protection Agency (EPA). The fundamentals of RCRA include ''cradle to grave'' management of hazardous waste, covering generators, transporters, and treatment, storage, and disposal facilities. The regulations also address extensive definitions and listing/identification mechanisms for hazardous waste along with a tracking system. Treatment is favored over disposal and emphasis is on ''front-end'' treatment such as waste minimization and pollution prevention. A study of large corporations such as Xerox, 3M, and Dow Chemical, as well as the public sector, has shown that well known and successful hazardous waste management programs emphasize pollution prevention and employment of techniques such as proactive environmental management, environmentally conscious manufacturing, and source reduction. Nearly all successful hazardous waste programs include some aspects of Total Quality Management, which begins with a strong commitment from top management. Hazardous waste management at the Rocky Flats Plant is further complicated by the dominance of ''mixed waste'' at the facility. The mixed waste stems from the original mission of the facility, which was production of nuclear weapons components for the Department of Energy (DOE). A Quality Assurance Program based on the criterion in DOE Order 5700.6C has been implemented at Rocky Flats. All of the elements of the Quality Assurance Program play a role in hazardous waste management. Perhaps one of the biggest waste management problems facing the Rocky Flats Plant is cleaning up contamination from a forty year mission which focused on production of nuclear weapon components
Long-range plan for buried transuranic waste studies at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Low, J.O.

1985-12-01

This document presents a plan to perform detailed studies of alternatives considered for the long-term management of buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The studies will provide the technical basis for DOE to make a decision on the future management of that waste. Although the waste is currently being handled in an acceptable manner, new solutions are continually being researched to improve management techniques. Three alternatives are being considered: (a) leave the waste as is; (b) improve in situ confinement of the waste; and (c) retrieve, process, and certify the waste for disposal at a federal repository. Fourteen studies are described in this plan for Alternatives 2 and 3. The leave-as-is alternative involves continuing present procedures for managing the buried waste. An ongoing environmental surveillance program, a low-level-waste stabilization program, and enhanced subsurface migration studies begun in FY-1984 at the INEL will provide data for the decision-making process for the INEL buried TRU waste. These ongoing studies for the leave-as-is alternative are summarized in this plan in limited detail. The improved-confinement alternative involves leaving the waste in place, but providing additional protection against wind, water penetration, erosion, and plant and animal intrusion. Several studies proposed under this alternative will examine special techniques to immobilize or encapsulate the buried waste. An in situ grouting study was implemented at the INEL starting in FY-1985 and will be completed at the end of FY-1986 with the grouting of a simulated INEL buried TRU waste trench. Studies of the third alternative will investigate improved retrieval, processing, and certification techniques. New equipment, such as industrial manipulators and excavating machinery, will be tested in the retrieval studies. Processing and certification studies will examine rapidly changing or new technologies
Vitrification of hazardous and radioactive wastes

International Nuclear Information System (INIS)

Bickford, D.F.; Schumacher, R.

1995-01-01

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
Hazardous Waste Research Center

Data.gov (United States)

Federal Laboratory Consortium — The U.S. Army Engineer Waterways Experiment Station (WES) is playing a major role in development of technologies for cleanup of toxic and hazardous waste in military...
T-Rex system for operation in TRU, LLW, and hazardous zones

International Nuclear Information System (INIS)

Kline, H.M.; Andreycheck, T.P.; Beeson, B.K.

1995-01-01

T-Rex stands for Transuranic Storage Area Remote Excavator that is dedicated to the retrieval of above ground waste containers and overburden at the Radioactive Waste Management Complex (RWMC) located at the Idaho National Engineering Laboratory. There are a number of sites around the world containing (transuranic) (TRU), low level (LLW), and hazardous wastes that requires teleoperated, heavy lift manipulators with long reach and high precision to handle the materials stored there. Remote operation of equipment will reduce the risk to personnel to as-low-as-reasonably-achievable (ALARA) levels. The T-Rex is designed to fulfill this requirement at relatively low cost through the integration of a production front shovel excavator with a control system, local and remote operator control stations, a closed-circuit television system (CCTV), and multiple end effectors with quick changeout capability. This paper describes the conversion of an off-the-shelf excavator to a machine utilizing a modified hydraulic system, an integrated onboard remote control system, CCTV system, collision avoidance system, and a remote control station
Transuranic radionuclides dispersed into the aquatic environment, a bibliography

Energy Technology Data Exchange (ETDEWEB)

Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

1994-04-01

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.
Avoiding the Hazards of Hazardous Waste.

Science.gov (United States)

Hiller, Richard

1996-01-01

Under a 1980 law, colleges and universities can be liable for cleanup of hazardous waste on properties, in companies, and related to stocks they invest in or are given. College planners should establish clear policy concerning gifts, investigate gifts, distance university from business purposes, sell real estate gifts quickly, consult a risk…
The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

Roberts, R.J.

1991-01-01

The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab
Audit Report on 'Waste Processing and Recovery Act Acceleration Efforts for Contact-Handled Transuranic Waste at the Hanford Site'

International Nuclear Information System (INIS)

2010-01-01

The Department of Energy's Office of Environmental Management's (EM), Richland Operations Office (Richland), is responsible for disposing of the Hanford Site's (Hanford) transuranic (TRU) waste, including nearly 12,000 cubic meters of radioactive contact-handled TRU wastes. Prior to disposing of this waste at the Department's Waste Isolation Pilot Plant (WIPP), Richland must certify that it meets WIPP's waste acceptance criteria. To be certified, the waste must be characterized, screened for prohibited items, treated (if necessary) and placed into a satisfactory disposal container. In a February 2008 amendment to an existing Record of Decision (Decision), the Department announced its plan to ship up to 8,764 cubic meters of contact-handled TRU waste from Hanford and other waste generator sites to the Advanced Mixed Waste Treatment Project (AMWTP) at Idaho's National Laboratory (INL) for processing and certification prior to disposal at WIPP. The Department decided to maximize the use of the AMWTP's automated waste processing capabilities to compact and, thereby, reduce the volume of contact-handled TRU waste. Compaction reduces the number of shipments and permits WIPP to more efficiently use its limited TRU waste disposal capacity. The Decision noted that the use of AMWTP would avoid the time and expense of establishing a processing capability at other sites. In May 2009, EM allocated $229 million of American Recovery and Reinvestment Act of 2009 (Recovery Act) funds to support Hanford's Solid Waste Program, including Hanford's contact-handled TRU waste. Besides providing jobs, these funds were intended to accelerate cleanup in the short term. We initiated this audit to determine whether the Department was effectively using Recovery Act funds to accelerate processing of Hanford's contact-handled TRU waste. Relying on the availability of Recovery Act funds, the Department changed course and approved an alternative plan that could increase costs by about $25 million
Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

Sharples, F.E.; Eyman, L.D.

1986-01-01

The Hazardous and Solid Waste Amendments of 1984 have greatly expanded the universe of what, and who, is regulated under Resource Conservation and Recovery Act (RCRA). Handling requirements for hazardous waste are becoming increasingly more stringent, particularly where land disposal is concerned. DOE needs to begin actively pursuing strategies directed at keeping the management of LLW clearly separated from wastes that are legitimately regulated under RCRA. Such strategies would include instituting systemwide changes in internal management practices, establishing improved location standards for LLW disposal, and negotiating interagency compromise agreements to obtain variances from RCRA requirements where necessary and appropriate
Structural analysis of the TRansUranic PACkage Transporter (TRUPACT)

International Nuclear Information System (INIS)

Lamoreaux, G.H.; Sutherland, S.H.; Duffey, T.A.

1981-07-01

The TRansUranic PACkage Transporter (TRUPACT) is a Type B container under development at the Transportation Technology Center, Sandia National Laboratory, for use in the transportation of contact-handled transuranic waste. This report describes the numerical analyses of the container's response to end-on, side-on, and center of gravity over corner impacts on an unyielding surface following a 9 m free fall. The results of the analyses are compared to available experimental data. In general, the analytical predictions and experimental comparisons confirm the validity of the TRUPACT design concept
Results of Testing the Relative Oxidizing Hazard of Wipes and KMI Zeolite

Energy Technology Data Exchange (ETDEWEB)

Ams, Bridget Elaine [Los Alamos National Laboratory

2017-05-09

This report includes the results from testing performed on the relative oxidizing hazard of a number of organic sorbing wipe materials, as well as KMI zeolite. These studies were undertaken to address a need by the Los Alamos National Laboratory (LANL) Hazardous Materials Management group, which requires a material that can sorb small spills in a glovebox without creating a disposal hazard due to the potential for oxidation reactions, as requested in Request for Testing of Wipes and Zeolite for Los Alamos National Laboratory Hazardous Materials Group (NPl-7) (NPl-7-17-002) and Request for Testing of Chamois Material for Los Alamos National Laboratory Hazardous Materials Group (NPl-7) (NPl-7-17-005). This set oftests is a continuation of previous testing described in Results from Preparation and Testing of Sorbents Mixed with (DWT-RPT-003), which provided data for the Waste Isolation Pilot Plant's Basis of Knowledge. The Basis of Knowledge establishes criteria for evaluating transuranic (TRU) waste that contains oxidizing chemicals.
Hazardous waste treatment and environmental remediation research

International Nuclear Information System (INIS)

1989-01-01

Los Alamos National Laboratory (LANL) is currently evaluating hazardous waste treatment and environmental remediation technologies in existence and under development to determine applicability to remediation needs of the DOE facilities under the Albuquerque Operations Office and to determine areas of research need. To assist LANL is this effort, Science Applications International Corporation (SAIC) conducted an assessment of technologies and monitoring methods that have been demonstrated or are under development. The focus of this assessment is to: (1) identify existing technologies for hazardous waste treatment and environmental remediation of old waste sites; (2) identify technologies under development and the status of the technology; (3) assess new technologies that need development to provide adequate hazardous waste treatment and remedial action technologies for DOD and DOE sites; and (4) identify hazardous waste and remediation problems for environmental research and development. There are currently numerous research and development activities underway nationwide relating to environmental contaminants and the remediation of waste sites. To perform this effort, SAIC evaluated current technologies and monitoring methods development programs in EPA, DOD, and DOE, as these are the primary agencies through which developmental methods are being demonstrated. This report presents this evaluation and provides recommendations as to pertinent research needs or activities to address waste site contamination problems. The review and assessment have been conducted at a programmatic level; site-specific and contaminant-specific evaluations are being performed by LANL staff as a separate, related activity
Waste retrieval plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US DOE has prepared this plan to meet the requirements of Public Law 102579, the Waste Isolation Pilot Plant (WIPP) LWA, The purpose. is to demonstrate readiness to retrieve from the WIPP underground transuranic radioactive waste that will be used for testing should retrieval be needed. The WIPP, a potential geologic repository for transuranic wastes generated in national-defense activities, has been constructed in southeastern New Mexico. Because the transuranic wastes will remain radioactive for a very long time, the WIPP must reasonably ensure safe performance over thousands of years. The DOE therefore decided to develop the facility in phases, to preclude premature decisions and to conduct the performance assessments needed to demonstrate long-term safety. Surface facilities for receiving waste have been built, and considerable underground excavation, 2150 feet below the surface, has been completed. The next step is a test phase, including underground experiments called ''bin tests'' and ''alcove test(s)'' with contact-handled transuranic waste. The objective of these waste tests is to collect relevant data about the gas-generation potential and volatile organic compound (VOC) source term of the waste for developing a basis for demonstrating long term safety by compliance with the applicable disposal regulations (40 CFR 191, 264 and 268). The test phase will end when a decision is made to begin disposal in the WIPP or to terminate the project if regulatory compliance cannot be determined and demonstrated. Authorization to receive transuranic waste at the WIPP for the test phase is given by the WIPP LWA provided certain requirements are met
Encapsulation of hazardous wastes into agglomerates

International Nuclear Information System (INIS)

Guloy, A.

1992-01-01

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
Establishment of a facility for intrusive characterization of transuranic waste at the Nevada Test Site

International Nuclear Information System (INIS)

Foster, B.D.; Musick, R.G.; Pedalino, J.P.; Cowley, J.L.; Karney, C.C.; Kremer, J.L.

1998-01-01

This paper describes design and construction, project management, and testing results associated with the Waste Examination Facility (WEF) recently constructed at the Nevada Test Site (NTS). The WEF and associated systems were designed, procured, and constructed on an extremely tight budget and within a fast track schedule. Part 1 of this paper focuses on design and construction activities, Part 2 discusses project management of WEF design and construction activities, and Part 3 describes the results of the transuranic (TRU) waste examination pilot project conducted at the WEF. In Part 1, the waste examination process is described within the context of Waste Isolation Pilot Plant (WIPP) characterization requirements. Design criteria are described from operational and radiological protection considerations. The WEF engineered systems are described. These systems include isolation barriers using a glove box and secondary containment structure, high efficiency particulate air (HEPA) filtration and ventilation systems, differential pressure monitoring systems, and fire protection systems. In Part 2, the project management techniques used for ensuring that stringent cost/schedule requirements were met are described. The critical attributes of these management systems are described with an emphasis on team work. In Part 3, the results of a pilot project directed at performing intrusive characterization (i.e., examination) of TRU waste at the WEF are described. Project activities included cold and hot operations. Cold operations included operator training, facility systems walk down, and operational procedures validation. Hot operations included working with plutonium contaminated TRU waste and consisted of waste container breaching, waste examination, waste segregation, data collection, and waste repackaging
40 CFR 271.12 - Requirements for hazardous waste management facilities.

Science.gov (United States)

2010-07-01

... Requirements for Final Authorization § 271.12 Requirements for hazardous waste management facilities. The State shall have standards for hazardous waste management facilities which are equivalent to 40 CFR parts 264... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Requirements for hazardous waste...
Environmental, technical and technological aspects of hazardous waste management in Poland

Science.gov (United States)

Pyssa, Justyna

2017-10-01

The issue of recovery and disposal of hazardous waste is not a new concern. The waste comes from various processes and technologies and therefore the bigger emphasis should be placed on reducing quantities of generated hazardous waste (which is often connected with changes in the technology of manufacturing a given product) and limitation of their negative influence on natural environment. Plants specializing in waste processing processes should meet the so-called cardinal triad of conditions deciding on the full success of investment, and namely: economic effectiveness, ecological efficiency and social acceptance. The structure of generation of hazardous waste in EU-28 has been presented in the paper. Methods of hazardous waste disposal in Poland have been discussed. Economic and ecological criteria for the selection of technology of hazardous waste disposal have been analyzed. The influence of the hazardous waste on the environment is also presented. For four groups of waste, which are currently stored, alternative methods of disposal have been proposed.
Field application of innovative grouting agents for in situ stabilization of buried waste sites

International Nuclear Information System (INIS)

Loomis, G.G.; Farnsworth, R.K.

1997-01-01

This paper presents field applications for two innovative grouting agents that were used to in situ stabilize buried waste sites, via jet grouting. The two grouting agents include paraffin and a proprietary iron oxide based cement grout called TECT. These materials were tested in specially designed cold test pits that simulate buried transuranic waste at the Idaho National Engineering Laboratory (INEL). The field demonstrations were performed at the INEL in an area referred to as the Cold Test Pit, which is adjacent to the INEL Radioactive Waste Management Complex (RWMC). At the RWMC, 56,000 m 3 of transuranic (TRU) waste is co-mingled with over 170,000 m 3 of soil in shallow land burial. Improving the confinement of this waste is one of the options for final disposition of this waste. Using jet-grouting technology to inject these materials into the pore spaces of buried waste sites results in the creation of buried monolithic waste forms that simultaneously protect the waste from subsidence, while eliminating the migratory potential of hazardous and radioactive contaminants in the waste

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

International Nuclear Information System (INIS)

Shott, Gregory J.; Yucel, Vefa

2009-01-01

In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes. The Waste Isolation Pilot Plant is the only facility meeting these requirements. The National Research Council, however, has found that exhumation of buried TRU waste for disposal in a deep geologic repository may not be warranted when the effort, exposures, and expense of retrieval are not commensurate with the risk reduction achieved. The long-term risks of leaving the TRU waste in-place are evaluated in two probabilistic performance assessments. A composite analysis, assessing the dose from all disposed waste and interacting sources of residual contamination, estimates an annual total effective dose equivalent (TEDE) of 0.01 mSv, or 3 percent of the dose constraint. A 40 CFR 191 performance assessment also indicates there is reasonable assurance of meeting all requirements. The 40 CFR 191.15 annual mean TEDE for a member of the public is estimated to reach a maximum of 0.055 mSv at 10,000 years, or approximately 37 percent of the 0.15 mSv individual protection requirement. In both assessments greater than 99 percent of the dose is from co-disposed low-level waste. The simulated probability of the 40 CFR 191.13 cumulative release exceeding 1 and 10 times the release limit is estimated to be 0.0093 and less than 0.0001, respectively. Site characterization data and hydrologic process modeling support a conclusion of no groundwater pathway within 10,000 years. Monte Carlo uncertainty analysis indicates that there is reasonable assurance of meeting all regulatory requirements. Sensitivity analysis indicates that the results
Waste Management Program management plan. Revision 1

International Nuclear Information System (INIS)

1997-02-01

As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL
Integrated treatment process of hazardous and mixed wastes

International Nuclear Information System (INIS)

Shibuya, M.; Suzuki, K.; Fujimura, Y.; Nakashima, T.; Moriya, Y.

1993-01-01

An integrated waste treatment system was studied based on technologies developed for the treatment of liquid radioactive, organic, and aqueous wastes containing hazardous materials and soils contaminated with heavy metals. The system consists of submerged incineration, metal ion fixing and stabilization, and soil washing treatments. Introduction of this system allows for the simultaneous processing of toxic waste and contaminated soils. Hazardous organic wastes can be decomposed into harmless gases, and aqueous wastes can be converted into a dischargeable effluent. The contaminated soil is backfilled after the removal of toxic materials. Experimental data show that the integration system is practical for complicated toxic wastes
Remote-Handled Transuranic Content Codes

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions

2006-12-01

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR
Results of HWVP transuranic process waste treatment laboratory and pilot-scale filtration tests using specially ground zeolite

International Nuclear Information System (INIS)

Eakin, D.E.

1996-03-01

Process waste streams from the Hanford Waste Vitrification Plant (HWVP) may require treatment for cesium, strontium, and transuranic (TRU) element removal in order to meet criteria for incorporation in grout. The approach planned for cesium and strontium removal is ion exchange using a zeolite exchanger followed by filtration. Filtration using a pneumatic hydropulse filter is planned to remove TRU elements which are associated with process solids and to also remove zeolite bearing the cesium and strontium. The solids removed during filtration are recycled to the melter feed system to be incorporated into the HWVP glass product. Fluor Daniel, Inc., the architect-engineering firm for HWVP, recommended a Pneumatic Hydropulse (PHP) filter manufactured by Mott Metallurgical Corporation for use in the HWVP. The primary waste streams considered for application of zeolite contact and filtration are melter off-gas condensate from the submerged bed scrubber (SBS), and equipment decontamination solutions from the Decontamination Waste Treatment Tank (DWTT). Other waste streams could be treated depending on TRU element and radionuclide content. Laboratory and pilot-scale filtration tests were conducted to provide a preliminary assessment of the adequacy of the recommended filter for application to HWVP waste treatment
Tritium Packages and 17th RH Canister Categories of Transuranic Waste Stored Below Ground within Area G

Energy Technology Data Exchange (ETDEWEB)

Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-01

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is a settlement agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Tritium Packages and 17th RH Canister categories; their physical and radiological characteristics; the results of the radioassays; and potential issues in retrieval and processing of the waste containers.
Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

2006-01-01

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)
Sampling and decontamination plan for the Transuranic Storage Area--1/-R container storage unit

International Nuclear Information System (INIS)

Barry, G.A.

1992-11-01

This document describes the sampling and decontamination of the Transuranic Storage Area (TSA)-l/-R container storage area and the earthen-covered portion of the TSA-2 container storage unit at the Radioactive Waste Management Complex. Stored containers from the earthen-covered asphalt pads will be retrieved from the TSA-l/-R and TSA-2 container storage units. Container retrieval will be conducted under the TSA retrieval enclosure, a fabricated steel building to be constructed over the earthen-covered pad to provide containment and weather protection. Following container retrieval, the TSA retrieval enclosure will be decontaminated to remove radioactive and hazardous contamination. The underlying soils will be sampled and analyzed to determine whether any contaminated soils require removal
TRU-ART: A cost-effective prototypical neutron imaging technique for transuranic waste certification systems

International Nuclear Information System (INIS)

Horton, W.S.

1989-01-01

The certification of defense radioactive waste as either transuranic or low-level waste requires very sensitive and accurate assay instrumentation to determine the specific radioactivity within an individual waste package. An assay instrument that employs a new technique (TRU-ART), which can identify the location of the radioactive material within a waste package, was designed, fabricated, and tested to potentially enhance the certification of problem defense waste drums. In addition, the assay instrumentation has potential application in radioactive waste reprocessing and neutron tomography. The assay instrumentation uses optimized electronic signal responses from an array of boral- and cadmium-shielded polyethylene-moderated 3 H detector packages. Normally, thermal neutrons that are detected by 3 H detectors have very poor spatial dependency that may be used to determine the location of the radioactive material. However, these shielded-detector packages of the TRU-ART system maintain the spatial dependency of the radioactive material in that the point of fast neutron thermalization is immediately adjacent to the 3 H detector. The TRU-ART was used to determine the location of radioactive material within three mock-up drums (empty, peat moss, and concrete) and four actual waste drums. The TRU-ART technique is very analogous to emission tomography. The mock-up drum and actual waste drum data, which were collected by the TRU-ART, were directly input into a algebraic reconstruction code to produce three-dimensional isoplots. Finally, a comprehensive fabrication cost estimate of the fielded drum assay system and the TRU-ART system was determined, and, subsequently, these estimates were used in a cost-benefit analysis to compare the economic advantage of the respective systems
Status report on the fluidized bed incineration system for U.S. Energy Research and Development Administration transuranic waste, January--June 1976

International Nuclear Information System (INIS)

Ziegler, D.L.; Richey, L.L.; Johnson, A.J.; Teter, A.L.; Feng, P.K.; Peterson, D.J.; Meile, L.J.

1977-01-01

A fluidized-bed incineration facility is being designed for installation at the Rocky Flats Plant to develop and demonstrate the process for the combustion of transuranic waste. The unit capacity will be about 82 kg/hr of combustible waste. The combustion process will utilize in situ neutralization of acid gases generated in the process. The equipment design is based on data generated on a pilot scale unit and represents a scale-up factor of nine. Title II engineering is at least 70 percent complete and construction work has begun
Radiolytic generation of chloro-organic compounds in transuranic and low-level radioactive waste

International Nuclear Information System (INIS)

Reed, D.T.; Armstrong, S.C.; Krause, T.R.

1993-01-01

The radiolytic degradation of chloro-plastics is being investigated to evaluate the formation of chlorinated volatile organic compounds in radioactive waste. These chlorinated VOCs, when their subsequent migration in the geosphere is considered, are potential sources of ground-water contamination. This contamination is an important consideration for transuranic waste repositories being proposed for the Waste Isolation Pilot Plant project and the several additional low-level radioactive waste sites being considered throughout the United States. The production of chlorinated volatile organic compounds due to the interaction of ionizing radiation with chloro-plastic materials has been well-established in both this work and past studies. This occurs as a result of gamma, beta, and alpha particle interactions with the plastic material. The assemblage of organic compounds generated depends on the type of plastic material, the type of ionizing radiation, the gaseous environment present and the irradiation temperature. In the authors' experiments, gas generation data were obtained by mounting representative plastics near (3 mm) an alpha particle source (Am-241 foil). This assembly was placed in an irradiation vessel which contained air, nitrogen, or a hydrogen/carbon dioxide mixture, at near-atmospheric pressures, to simulate the range of atmospheres likely to be encountered in the subsurface. The gas phase in the vessels are periodically sampled for net gas production. The gas phase concentrations are monitored over time to determine trends and calculate the radiolytic yield for the various gaseous products
Immobilisation of hazardous waste

International Nuclear Information System (INIS)

Cope, C.B.

1983-01-01

Hazardous waste, e.g. radioactive waste, particularly that containing caesium-137, is immobilised by mixing with cement and solidifiable organic polymeric material. When first mixed, the organic material is preferably liquid and at this time can be polymerisable or already polymerised. The hardening can result from cooling or further polymerisation e.g. cross-linking. The organic material may be wax, or a polyester which may be unsaturated and cross-linkable by reaction with styrene. (author)
National information network and database system of hazardous waste management in China

Energy Technology Data Exchange (ETDEWEB)

Ma Hongchang [National Environmental Protection Agency, Beijing (China)

1996-12-31

Industries in China generate large volumes of hazardous waste, which makes it essential for the nation to pay more attention to hazardous waste management. National laws and regulations, waste surveys, and manifest tracking and permission systems have been initiated. Some centralized hazardous waste disposal facilities are under construction. China`s National Environmental Protection Agency (NEPA) has also obtained valuable information on hazardous waste management from developed countries. To effectively share this information with local environmental protection bureaus, NEPA developed a national information network and database system for hazardous waste management. This information network will have such functions as information collection, inquiry, and connection. The long-term objective is to establish and develop a national and local hazardous waste management information network. This network will significantly help decision makers and researchers because it will be easy to obtain information (e.g., experiences of developed countries in hazardous waste management) to enhance hazardous waste management in China. The information network consists of five parts: technology consulting, import-export management, regulation inquiry, waste survey, and literature inquiry.
De-Inventory Plan for Transuranic Waste Stored at Area G

Energy Technology Data Exchange (ETDEWEB)

Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Christensen, Davis V. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Shepard, Mark D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-06-21

This report describes the strategy and detailed work plan developed by Los Alamos National Laboratory (LANL) to disposition transuranic (TRU) waste stored at its Area G radioactive waste storage site. The focus at this time is on disposition of 3,706 m³ of TRU waste stored above grade by June 30, 2014, which is one of the commitments within the Framework Agreement: Realignment of Environmental Priorities between the Department of Energy (DOE) National Nuclear Security Administration (NNSA) and the State of New Mexico Environment Department (NMED), Reference 1. A detailed project management schedule has been developed to manage this work and better ensure that all required activities are aligned and integrated. The schedule was developed in conjunction with personnel from the NNSA Los Alamos Site Office (LASO), the DOE Carlsbad Field Office (CBFO), the Central Characterization Project (CCP), and Los Alamos National Security, LLC (LANS). A detailed project management schedule for the remainder of the above grade inventory and the below grade inventory will be developed and incorporated into the De-Inventory Plan by December 31, 2012. This schedule will also include all newly-generated TRU waste received at Area G in FYs 2012 and 2013, which must be removed by no later than December 31, 2014, under the Framework Agreement. The TRU waste stored above grade at Area G is considered to be one of the highest nuclear safety risks at LANL, and the Defense Nuclear Facility Safety Board has expressed concern for the radioactive material at risk (MAR) contained within the above grade TRU waste inventory and has formally requested that DOE reduce the MAR. A large wildfire called the Las Conchas Fire burned extensive areas west of LANL in late June and July 2011. Although there was minimal to no impact by the fire to LANL, the fire heightened public concern and news media attention on TRU waste storage at Area G. After the fire, New Mexico Governor Susana Martinez also
Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management: Waste reduction workshop 7

International Nuclear Information System (INIS)

1991-11-01

The focus of this workshop was on goal setting and the methods of establishing meaningful goals for a waste minimization program. These workshops assist DOE waste-generating sites in implementing waste minimization plans and programs, thus providing for optimal waste reduction within the DOE complex. All wastes are considered liquid, solid, and airborne within the categories of high-level waste, transuranic waste (TRU), low-level waste (LLW), hazardous waste, mixed waste, office waste, and sanitary waste. Topics of discussion within workshops encompass a wide range of subjects. Subjects include any method or technical activity from waste generation to disposal, such as process design or improvements, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration is also given to activities for remedial action and for decontamination and decommissioning
EVALUATION OF ALTERNATIVE STRONIUM AND TRANSURANIC SEPARATION PROCESSES

Energy Technology Data Exchange (ETDEWEB)

SMALLEY CS

2011-04-25

In order to meet contract requirements on the concentrations of strontium-90 and transuranic isotopes in the immobilized low-activity waste, strontium-90 and transuranics must be removed from the supernate of tanks 241-AN-102 and 241-AN-107. The process currently proposed for this application is an in-tank precipitation process using strontium nitrate and sodium permanganate. Development work on the process has not proceeded since 2005. The purpose of the evaluation is to identify whether any promising alternative processes have been developed since this issue was last examined, evaluate the alternatives and the baseline process, and recommend which process should be carried forward.
Potential microbial impact on transuranic wastes under conditions expected in the Waste Isolation Pilot Plant (WIPP). Annual report, October 1, 1978-September 30, 1979

International Nuclear Information System (INIS)

Barnhart, B.J.; Campbell, E.W.; Martinez, E.; Caldwell, D.E.; Hallett, R.

1980-07-01

Previous results were confirmed showing elevated frequencies of radiation-resistant bacteria in microorganisms isolated from shallow transuranic (TRU) burial soil that exhibits nanocurie levels of beta and gamma radioactivity. Research to determine whether plutonium could be methylated by the microbially produced methyl donor, methylcobalamine, was terminated when literature and consulting radiochemists confirmed that other alkylated transuranic elements are extremely short-lived in the presence of oxygen. Emphasis was placed on investigation of the dissolution of plutonium dioxide by complex formation between plutonium and a polyhydroxamate chelate similar to that produced by microorganisms. New chromatographic and spectrophotometric evidence supports previous results showing enhanced dissolution of alpha radioactivity when 239 Pu dioxide was mixed with the chelate Desferol. Microbial degradation studies of citrate, ethylenediamine tetraacetate (EDTA), and nitrilo triacetate (NTA) chelates of europium are in progress. Current results are summarized. All of the chelates were found to degrade. The average half-life for citrate, NTA, and EDTA was 3.2, 8.0, and 28 years, respectively. Microbial CO 2 generation is also in progress in 72 tests on several waste matrices under potential WIPP isolation conditions. The mean rate of gas generation was 5.97 μg CO 2 /g waste/day. Increasing temperature increased rates of microbial gas generation across treatments of brine, varying water content, nutrient additions, and anaerobic conditions. No microbial growth was detected in experiments to enumerate and identify the microorganisms in rocksalt cores from the proposed WIPP site. This report contains the year's research results and recommendations derived for the design of safe storage of TRU wastes under geologic repository conditions
Waste reduction at the Savannah River Site

International Nuclear Information System (INIS)

Stevens, W.E.; Lee, R.A.; Reynolds, R.W.

1990-01-01

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities
Removal of strontium and transuranics from Hanford tank waste via addition of metal cations and chemical oxidant: FY 1995 test results

International Nuclear Information System (INIS)

Orth, R.J.; Zacher, A.H.; Schmidt, A.J.; Elmore, M.R.; Elliott, K.R.; Neuenschwander, G.G.; Gano, S.R.

1995-09-01

Chelating organics and some of their degradation products in the Hanford tank waste, such as EDTA, HEDTA, and NTA act to solubilize strontium and transuranics (TRU) in the tank waste supernatant. Displacement of strontium and TRU will facilitate the removal of these radionuclides via precipitation/filtration, ion exchange, or solvent extraction so that low-level waste feed specifications can be met. Pacific Northwest Laboratory has investigated two methods for releasing organic-complexed strontium and TRU components to allow for effective pretreatment of tank waste supernatant: metal cation addition (to promote displacement and flocculation) and chemical oxidant (pennanganate) addition (to promote chelator destruction/defunctionalization and possibly flocculation). These methods, which can be conducted at near-ambient. temperatures and pressures, could be deployed as intank processes
WHO collaboration in hazardous waste management in the Western Pacific Region

Energy Technology Data Exchange (ETDEWEB)

Ogawa, Hisashi [Western Pacific Regional Environmental Health Centre, Kuala Lumpur (Malaysia)

1996-12-31

Since April 1989 when the World Health Organization`s (WHO`s) activities in hazardous waste management in the Western Pacific Region were presented at the Pacific Basin Conference in Singapore, WHO and its Member States have carried out a number of collaborative activities in hazardous waste management. These activities focused on three main areas: national capacity building in the management of toxic chemicals and hazardous wastes in rapidly industrializing countries, management of clinical or medical waste, and hazardous waste management in Pacific Island countries. This paper summarizes these collaborative activities, identifies the main problems and issues encountered, and discusses future prospects of WHO collaboration with its Member States in the area of hazardous waste management. 1 fig., 1 tab.

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