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Sample records for llnl waste minimization

  1. LLNL Waste Minimization Program Plan

    International Nuclear Information System (INIS)

    1990-01-01

    This document is the February 14, 1990 version of the LLNL Waste Minimization Program Plan (WMPP). The Waste Minimization Policy field has undergone continuous changes since its formal inception in the 1984 HSWA legislation. The first LLNL WMPP, Revision A, is dated March 1985. A series of informal revision were made on approximately a semi-annual basis. This Revision 2 is the third formal issuance of the WMPP document. EPA has issued a proposed new policy statement on source reduction and recycling. This policy reflects a preventative strategy to reduce or eliminate the generation of environmentally-harmful pollutants which may be released to the air, land surface, water, or ground water. In accordance with this new policy new guidance to hazardous waste generators on the elements of a Waste Minimization Program was issued. In response to these policies, DOE has revised and issued implementation guidance for DOE Order 5400.1, Waste Minimization Plan and Waste Reduction reporting of DOE Hazardous, Radioactive, and Radioactive Mixed Wastes, final draft January 1990. This WMPP is formatted to meet the current DOE guidance outlines. The current WMPP will be revised to reflect all of these proposed changes when guidelines are established. Updates, changes and revisions to the overall LLNL WMPP will be made as appropriate to reflect ever-changing regulatory requirements. 3 figs., 4 tabs

  2. LLNL Waste Minimization Program Plan

    International Nuclear Information System (INIS)

    1990-05-01

    This document is the February 14, 1990 version of the LLNL Waste Minimization Program Plan (WMPP). Now legislation at the federal level is being introduced. Passage will result in new EPA regulations and also DOE orders. At the state level the Hazardous Waste Reduction and Management Review Act of 1989 was signed by the Governor. DHS is currently promulgating regulations to implement the new law. EPA has issued a proposed new policy statement on source reduction and recycling. This policy reflects a preventative strategy to reduce or eliminate the generation of environmentally-harmful pollutants which may be released to the air, land surface, water, or ground water. In accordance with this policy new guidance to hazardous waste generators on the elements of a Waste Minimization Program was issued. This WMPP is formatted to meet the current DOE guidance outlines. The current WMPP will be revised to reflect all of these proposed changes when guidelines are established. Updates, changes and revisions to the overall LLNL WMPP will be made as appropriate to reflect ever-changing regulatory requirements

  3. Lawrence Livermore National Laboratory (LLNL) Waste Minimization Program Plan

    International Nuclear Information System (INIS)

    Heckman, R.A.; Tang, W.R.

    1989-01-01

    This Program Plan document describes the background of the Waste Minimization field at Lawrence Livermore National Laboratory (LLNL) and refers to the significant studies that have impacted on legislative efforts, both at the federal and state levels. A short history of formal LLNL waste minimization efforts is provided. Also included are general findings from analysis of work to date, with emphasis on source reduction findings. A short summary is provided on current regulations and probable future legislation which may impact on waste minimization methodology. The LLN Waste Minimization Program Plan is designed to be dynamic and flexible so as to meet current regulations, and yet is able to respond to an everchanging regulatory environment. 19 refs., 12 figs., 8 tabs

  4. Waste minimization activity report for 1991

    International Nuclear Information System (INIS)

    Shoemaker, J.D.

    1992-01-01

    This is a waste reduction report for the Lawrence Livermore National Laboratory (LLNL) for 1991. The report covers the Main Site at Livermore and Site 300. Each research program at LLNL is described by its operation, administrative procedures, and waste minimization. Examples of the programs at LLNL are biomedical and environmental research, chemistry and materials science, and energy program and earth sciences. (MB)

  5. 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.

  6. 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

  7. LLNL/YMP Waste Container Fabrication and Closure Project

    International Nuclear Information System (INIS)

    1990-10-01

    The Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes

  8. Waste minimization and pollution prevention awareness plan

    Energy Technology Data Exchange (ETDEWEB)

    1991-05-31

    The purpose of this plan is to document the Lawrence Livermore National Laboratory (LLNL) Waste Minimization and Pollution Prevention Awareness Program. The plan specifies those activities and methods that are or will be employed to reduce the quantity and toxicity of wastes generated at the site. The intent of this plan is to respond to and comply with (DOE's) policy and guidelines concerning the need for pollution prevention. The Plan is composed of a LLNL Waste Minimization and Pollution Prevention Awareness Program Plan and, as attachments, Program- and Department-specific waste minimization plans. This format reflects the fact that waste minimization is considered a line management responsibility and is to be addressed by each of the Programs and Departments. 14 refs.

  9. Waste minimization and pollution prevention awareness plan

    International Nuclear Information System (INIS)

    1991-01-01

    The purpose of this plan is to document the Lawrence Livermore National Laboratory (LLNL) Waste Minimization and Pollution Prevention Awareness Program. The plan specifies those activities and methods that are or will be employed to reduce the quantity and toxicity of wastes generated at the site. The intent of this plan is to respond to and comply with (DOE's) policy and guidelines concerning the need for pollution prevention. The Plan is composed of a LLNL Waste Minimization and Pollution Prevention Awareness Program Plan and, as attachments, Program- and Department-specific waste minimization plans. This format reflects the fact that waste minimization is considered a line management responsibility and is to be addressed by each of the Programs and Departments. 14 refs

  10. Review of LLNL Mixed Waste Streams for the Application of Potential Waste Reduction Controls

    International Nuclear Information System (INIS)

    Belue, A; Fischer, R P

    2007-01-01

    In July 2004, LLNL adopted the International Standard ISO 14001 as a Work Smart Standard in lieu of DOE Order 450.1. In support of this new requirement the Director issued a new environmental policy that was documented in Section 3.0 of Document 1.2, ''ES and H Policies of LLNL'', in the ES and H Manual. In recent years the Environmental Management System (EMS) process has become formalized as LLNL adopted ISO 14001 as part of the contract under which the laboratory is operated for the Department of Energy (DOE). On May 9, 2005, LLNL revised its Integrated Safety Management System Description to enhance existing environmental requirements to meet ISO 14001. Effective October 1, 2005, each new project or activity is required to be evaluated from an environmental aspect, particularly if a potential exists for significant environmental impacts. Authorizing organizations are required to consider the management of all environmental aspects, the applicable regulatory requirements, and reasonable actions that can be taken to reduce negative environmental impacts. During 2006, LLNL has worked to implement the corrective actions addressing the deficiencies identified in the DOE/LSO audit. LLNL has begun to update the present EMS to meet the requirements of ISO 14001:2004. The EMS commits LLNL--and each employee--to responsible stewardship of all the environmental resources in our care. The generation of mixed radioactive waste was identified as a significant environmental aspect. Mixed waste for the purposes of this report is defined as waste materials containing both hazardous chemical and radioactive constituents. Significant environmental aspects require that an Environmental Management Plan (EMP) be developed. The objective of the EMP developed for mixed waste (EMP-005) is to evaluate options for reducing the amount of mixed waste generated. This document presents the findings of the evaluation of mixed waste generated at LLNL and a proposed plan for reduction

  11. Advanced pyrochemical technologies for minimizing nuclear waste

    International Nuclear Information System (INIS)

    Bronson, M.C.; Dodson, K.E.; Riley, D.C.

    1994-01-01

    The Department of Energy (DOE) is seeking to reduce the size of the current nuclear weapons complex and consequently minimize operating costs. To meet this DOE objective, the national laboratories have been asked to develop advanced technologies that take uranium and plutonium, from retired weapons and prepare it for new weapons, long-term storage, and/or final disposition. Current pyrochemical processes generate residue salts and ceramic wastes that require aqueous processing to remove and recover the actinides. However, the aqueous treatment of these residues generates an estimated 100 liters of acidic transuranic (TRU) waste per kilogram of plutonium in the residue. Lawrence Livermore National Laboratory (LLNL) is developing pyrochemical techniques to eliminate, minimize, or more efficiently treat these residue streams. This paper will present technologies being developed at LLNL on advanced materials for actinide containment, reactors that minimize residues, and pyrochemical processes that remove actinides from waste salts

  12. Waste Minimization and Pollution Prevention Awareness Plan

    International Nuclear Information System (INIS)

    1994-04-01

    The purpose of this plan is to document Lawrence Livermore National Laboratory (LLNL) projections for present and future waste minimization and pollution prevention. The plan specifies those activities and methods that are or will be used to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) requirements. This Plan provides an overview of projected activities from FY 1994 through FY 1999. The plans are broken into site-wide and problem-specific activities. All directorates at LLNL have had an opportunity to contribute input, to estimate budget, and to review the plan. In addition to the above, this plan records LLNL's goals for pollution prevention, regulatory drivers for those activities, assumptions on which the cost estimates are based, analyses of the strengths of the projects, and the barriers to increasing pollution prevention activities

  13. LLNL radioactive waste management plan as per DOE Order 5820.2

    International Nuclear Information System (INIS)

    1984-01-01

    The following aspects of LLNL's radioactive waste management plan are discussed: program administration; description of waste generating processes; radioactive waste collection, treatment, and disposal; sanitary waste management; site 300 operations; schedules and major milestones for waste management activities; and environmental monitoring programs (sampling and analysis)

  14. Waste Minimization and Pollution Prevention Awareness Plan

    International Nuclear Information System (INIS)

    1992-01-01

    The purpose of this plan is to document the Lawrence Livermore National Laboratory (LLNL) Waste Minimization and Pollution Prevention Awareness Program. The plan specifies those activities and methods that are or will be employed to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) and other legal requirements that are discussed in Section C, below. The Pollution Prevention Awareness Program is included with the Waste Minimization Program as suggested by DOE Order 5400.1. The intent of this plan is to respond to and comply with the Department's policy and guidelines concerning the need for pollution prevention. The Plan is composed of a LLNL Waste Minimization and Pollution Prevention Awareness Program Plan and, as attachments, Directorate-, Program- and Department-specific waste minimization plans. This format reflects the fact that waste minimization is considered a line management responsibility and is to be addressed by each of the Directorates, Programs and Departments. Several Directorates have been reorganized, necessitating changes in the Directorate plans that were published in 1991

  15. Waste minimization assessment procedure

    International Nuclear Information System (INIS)

    Kellythorne, L.L.

    1993-01-01

    Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative

  16. Hazardous waste minimization

    International Nuclear Information System (INIS)

    Freeman, H.

    1990-01-01

    This book presents an overview of waste minimization. Covers applications of technology to waste reduction, techniques for implementing programs, incorporation of programs into R and D, strategies for private industry and the public sector, and case studies of programs already in effect

  17. LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-10-01

    The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

  18. Waste minimization and pollution prevention awareness plan. Revision 1

    International Nuclear Information System (INIS)

    1994-07-01

    The purpose of this plan is to document Lawrence Livermore National Laboratory (LLNL) projections for present and future waste minimization and pollution prevention. The plan specifies those activities and methods that are or will be used to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) requirements. This Waste Minimization and Pollution Prevention Awareness Plan provides an overview of projected activities from FY 1994 through FY 1999. The plans are broken into site-wide and problem-specific activities. All directorates at LLNL have had an opportunity to contribute input, estimate budgets, and review the plan. In addition to the above, this plan records LLNL's goals for pollution prevention, regulatory drivers for those activities, assumptions on which the cost estimates are based, analyses of the strengths of the projects, and the barriers to increasing pollution prevention activities

  19. Legal incentives for minimizing waste

    International Nuclear Information System (INIS)

    Clearwater, S.W.; Scanlon, J.M.

    1991-01-01

    Waste minimization, or pollution prevention, has become an integral component of federal and state environmental regulation. Minimizing waste offers many economic and public relations benefits. In addition, waste minimization efforts can also dramatically reduce potential criminal requirements. This paper addresses the legal incentives for minimizing waste under current and proposed environmental laws and regulations

  20. Assessment of the proposed decontamination and waste treatment facility at LLNL

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1987-01-01

    To provide a centralized decontamination and waste treatment facility (DWTF) at LLNL, the construction of a new installation has been planned. Objectives for this new facility were to replace obsolete, structurally and environmentally sub-marginal liquid and solid waste process facilities and decontamination facility and to bring these facilities into compliance with existing federal, state and local regulations as well as DOE orders. In a previous study, SAIC conducted a preliminary review and evaluation of existing facilities at LLNL and cost effectiveness of the proposed DWTF. This document reports on a detailed review of specific aspects of the proposed DWTF

  1. Guidelines for mixed waste minimization

    International Nuclear Information System (INIS)

    Owens, C.

    1992-02-01

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

  2. Minimizing waste in environmental restoration

    International Nuclear Information System (INIS)

    Moos, L.; Thuot, J.R.

    1996-01-01

    Environmental restoration, decontamination and decommissioning and facility dismantelment projects are not typically known for their waste minimization and pollution prevention efforts. Typical projects are driven by schedules and milestones with little attention given to cost or waste minimization. Conventional wisdom in these projects is that the waste already exists and cannot be reduced or minimized. In fact, however, there are three significant areas where waste and cost can be reduced. Waste reduction can occur in three ways: beneficial reuse or recycling; segregation of waste types; and reducing generation of secondary waste. This paper will discuss several examples of reuse, recycle, segregation, and secondary waste reduction at ANL restoration programs

  3. Minimization of mixed waste in explosive testing operations

    International Nuclear Information System (INIS)

    Gonzalez, M.A.; Sator, F.E.; Simmons, L.F.

    1993-02-01

    In the 1970s and 1980s, efforts to manage mixed waste and reduce pollution focused largely on post-process measures. In the late 1980s, the approach to waste management and pollution control changed, focusing on minimization and prevention rather than abatement, treatment, and disposal. The new approach, and the formulated guidance from the US Department of Energy, was to take all necessary measures to minimize waste and prevent the release of pollutants to the environment. Two measures emphasized in particular were source reduction (reducing the volume and toxicity of the waste source) and recycling. In 1988, a waste minimization and pollution prevention program was initiated at Site 300, where the Lawrence Livermore National Laboratory (LLNL) conducts explosives testing. LLNL's Defense Systems/Nuclear Design (DS/ND) Program has adopted a variety of conservation techniques to minimize waste generation and cut disposal costs associated with ongoing operations. The techniques include minimizing the generation of depleted uranium and lead mixed waste through inventory control and material substitution measures and through developing a management system to recycle surplus explosives. The changes implemented have reduced annual mixed waste volumes by more than 95% and reduced overall radioactive waste generation (low-level and mixed) by more than 75%. The measures employed were cost-effective and easily implemented

  4. Minimizing waste in environmental restoration

    International Nuclear Information System (INIS)

    Thuot, J.R.; Moos, L.

    1996-01-01

    Environmental restoration, decontamination and decommissioning, and facility dismantlement projects are not typically known for their waste minimization and pollution prevention efforts. Typical projects are driven by schedules and milestones with little attention given to cost or waste minimization. Conventional wisdom in these projects is that the waste already exists and cannot be reduced or minimized; however, there are significant areas where waste and cost can be reduced by careful planning and execution. Waste reduction can occur in three ways: beneficial reuse or recycling, segregation of waste types, and reducing generation of secondary waste

  5. Waste minimization handbook, Volume 1

    International Nuclear Information System (INIS)

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

    1995-12-01

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

  6. Waste minimization handbook, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-12-01

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

  7. Annual Waste Minimization Summary Report

    International Nuclear Information System (INIS)

    Haworth, D.M.

    2011-01-01

    This report summarizes the waste minimization efforts undertaken by National Security TechnoIogies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2010. The NNSA/NSO Pollution Prevention Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment.

  8. Implementing necessary and sufficient standards for radioactive waste management at LLNL

    International Nuclear Information System (INIS)

    Sims, J.M.; Ladran, A.; Hoyt, D.

    1995-01-01

    Lawrence Livermore National Laboratory (LLNL) and the U.S. Department of Energy, Oakland Field Office (DOE/OAK), are participating in a pilot program to evaluate the process to develop necessary and sufficient sets of standards for contractor activities. This concept of contractor and DOE jointly and locally deciding on what constitutes the set of standards that are necessary and sufficient to perform work safely and in compliance with federal, state, and local regulations, grew out of DOE's Department Standards Committee (Criteria for the Department's Standards Program, August 1994, DOE/EH/-0416). We have chosen radioactive waste management activities as the pilot program at LLNL. This pilot includes low-level radioactive waste, transuranic (TRU) waste, and the radioactive component of low-level and TRU mixed wastes. Guidance for the development and implementation of the necessary and sufficient set of standards is provided in open-quotes The Department of Energy Closure Process for Necessary and Sufficient Sets of Standards,close quotes March 27, 1995 (draft)

  9. How to minimize wastes

    International Nuclear Information System (INIS)

    Ambolet, M.

    1988-10-01

    Actions undertaken by the CEA to decrease the stock of natural and depleted uranium are presented in this paper. Various wastes and residues are produced in uranium fabrication. If for some wastes or residues processing methods were found previously, for other storage was the rule. Facing growing problems of safety, bulkiness, and cost new treatments allow to decrease a great amount of wastes. Uranium fabrication cycle, wastes and residues are described. Processing of the different residues of operations and optimization of manufacture are indicated [fr

  10. Summary of LLNL's accomplishments for the FY93 Waste Processing Operations Program

    International Nuclear Information System (INIS)

    Grasz, E.; Domning, E.; Heggins, D.; Huber, L.; Hurd, R.; Martz, H.; Roberson, P.; Wilhelmsen, K.

    1994-04-01

    Under the US Department of Energy's (DOE's) Office of Technology Development (OTD)-Robotic Technology Development Program (RTDP), the Waste Processing Operations (WPO) Program was initiated in FY92 to address the development of automated material handling and automated chemical and physical processing systems for mixed wastes. The Program's mission was to develop a strategy for the treatment of all DOE mixed, low-level, and transuranic wastes. As part of this mission, DOE's Mixed Waste Integrated Program (MWIP) was charged with the development of innovative waste treatment technologies to surmount shortcomings of existing baseline systems. Current technology advancements and applications results from cooperation of private industry, educational institutions, and several national laboratories operated for DOE. This summary document presents the LLNL Environmental Restoration and Waste Management (ER and WM) Automation and Robotics Section's contributions in support of DOE's FY93 WPO Program. This document further describes the technological developments that were integrated in the 1993 Mixed Waste Operations (MWO) Demonstration held at SRTC in November 1993

  11. 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

  12. Waste minimization in analytical methods

    International Nuclear Information System (INIS)

    Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S. Schilling, J.B.

    1995-01-01

    The US Department of Energy (DOE) will require a large number of waste characterizations over a multi-year period to accomplish the Department's goals in environmental restoration and waste management. Estimates vary, but two million analyses annually are expected. The waste generated by the analytical procedures used for characterizations is a significant source of new DOE waste. Success in reducing the volume of secondary waste and the costs of handling this waste would significantly decrease the overall cost of this DOE program. Selection of appropriate analytical methods depends on the intended use of the resultant data. It is not always necessary to use a high-powered analytical method, typically at higher cost, to obtain data needed to make decisions about waste management. Indeed, for samples taken from some heterogeneous systems, the meaning of high accuracy becomes clouded if the data generated are intended to measure a property of this system. Among the factors to be considered in selecting the analytical method are the lower limit of detection, accuracy, turnaround time, cost, reproducibility (precision), interferences, and simplicity. Occasionally, there must be tradeoffs among these factors to achieve the multiple goals of a characterization program. The purpose of the work described here is to add waste minimization to the list of characteristics to be considered. In this paper the authors present results of modifying analytical methods for waste characterization to reduce both the cost of analysis and volume of secondary wastes. Although tradeoffs may be required to minimize waste while still generating data of acceptable quality for the decision-making process, they have data demonstrating that wastes can be reduced in some cases without sacrificing accuracy or precision

  13. Waste minimization activities in the Materials Fabrication Division at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Dini, J.W.

    1991-08-01

    The mission of the Materials Fabrication Division (MFD) is to provide fabrication services and technology in support of all programs at Lawrence Livermore National Laboratory (LLNL). MFD involvement is called for when fabrication activity requires levels of expertise, technology, equipment, process development, hazardous processes, security, or scheduling that is typically not commercially available. Customers are encouraged to utilize private industry for fabrication activity requiring routine processing or for production applications. Our waste minimization (WM) program has been directed at source reduction and recycling in concert with the working definition of waste minimization used by EPA. The principal focus of WM activities has been on hazardous wastes as defined by RCRA, however, all pollutant emissions into air, water and land are being considered as part of the program. The incentives include: (1) economics, (2) regulatory conformance, (3) public image and (4) environmental concern. This report discusses the waste minimization program at LLNL

  14. Y-12 Plant waste minimization strategy

    International Nuclear Information System (INIS)

    Kane, M.A.

    1987-01-01

    The 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) mandate that waste minimization be a major element of hazardous waste management. In response to this mandate and the increasing costs for waste treatment, storage, and disposal, the Oak Ridge Y-12 Plant developed a waste minimization program to encompass all types of wastes. Thus, waste minimization has become an integral part of the overall waste management program. Unlike traditional approaches, waste minimization focuses on controlling waste at the beginning of production instead of the end. This approach includes: (1) substituting nonhazardous process materials for hazardous ones, (2) recycling or reusing waste effluents, (3) segregating nonhazardous waste from hazardous and radioactive waste, and (4) modifying processes to generate less waste or less toxic waste. An effective waste minimization program must provide the appropriate incentives for generators to reduce their waste and provide the necessary support mechanisms to identify opportunities for waste minimization. This presentation focuses on the Y-12 Plant's strategy to implement a comprehensive waste minimization program. This approach consists of four major program elements: (1) promotional campaign, (2) process evaluation for waste minimization opportunities, (3) waste generation tracking system, and (4) information exchange network. The presentation also examines some of the accomplishments of the program and issues which need to be resolved

  15. Assessment and cleanup of the Taxi Strip waste storage area at LLNL [Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Buerer, A.

    1983-01-01

    In September 1982 the Hazards Control Department of the Lawrence Livermore National Laboratory (LLNL) began a final radiological survey of a former low-level radioactive waste storage area called the Taxi Strip so that the area could be released for construction of an office building. Collection of soil samples at the location of a proposed sewer line led to the discovery of an old disposal pit containing soil contaminated with low-level radioactive waste and organic solvents. The Taxi Strip area was excavated leading to the discovery of three additional small pits. The clean-up of Pit No. 1 is considered to be complete for radioactive contamination. The results from the chlorinated solvent analysis of the borehole samples and the limited number of samples analyzed by gas chromatography/mass spectrometry indicate that solvent clean-up at this pit is complete. This is being verified by gas chromatography/mass spectrometry analysis of a few additional soil samples from the bottom sides and ends of the pit. As a precaution, samples are also being analyzed for metals to determine if further excavation is necessary. Clean-up of Pits No. 2 and No. 3 is considered to be complete for radioactive and solvent contamination. Results of analysis for metals will determine if excavation is complete. Excavation of Pit No. 4 which resulted from surface leakage of radioactive contamination from an evaporation tray is complete

  16. Mixed waste and waste minimization: The effect of regulations and waste minimization on the laboratory

    International Nuclear Information System (INIS)

    Dagan, E.B.; Selby, K.B.

    1993-08-01

    The Hanford Site is located in the State of Washington and is subject to state and federal environmental regulations that hamper waste minimization efforts. This paper addresses the negative effect of these regulations on waste minimization and mixed waste issues related to the Hanford Site. Also, issues are addressed concerning the regulations becoming more lenient. In addition to field operations, the Hanford Site is home to the Pacific Northwest Laboratory which has many ongoing waste minimization activities of particular interest to laboratories

  17. Design and construction of a 208-L drum containing representative LLNL transuranic and low-level wastes

    International Nuclear Information System (INIS)

    Camp, D.C.; Pickering, J.; Martz, H.E.

    1994-01-01

    At the Lawrence Livermore National Laboratory (LLNL), we are developing the nondestructive analysis (NDA) technique of active (A) computed tomography (CT) to measure waste matrix attenuation as a function of gamma-ray energy (ACT); and passive. (P) Cr to locate and identify all gamma-ray emitting isotopes within a waste container. Coupling the ACT and PCT results will quantify each isotope identified, thereby categorize the amount of radioactivity within waste drums having volumes up to 416-liters (L), i.e., 110-gallon drums

  18. Westinghouse Hanford Company waste minimization actions

    International Nuclear Information System (INIS)

    Greenhalgh, W.O.

    1988-09-01

    Companies that generate hazardous waste materials are now required by national regulations to establish a waste minimization program. Accordingly, in FY88 the Westinghouse Hanford Company formed a waste minimization team organization. The purpose of the team is to assist the company in its efforts to minimize the generation of waste, train personnel on waste minimization techniques, document successful waste minimization effects, track dollar savings realized, and to publicize and administer an employee incentive program. A number of significant actions have been successful, resulting in the savings of materials and dollars. The team itself has been successful in establishing some worthwhile minimization projects. This document briefly describes the waste minimization actions that have been successful to date. 2 refs., 26 figs., 3 tabs

  19. Waste Minimization Measurement and Progress Reporting

    International Nuclear Information System (INIS)

    Stone, K.A.

    1995-01-01

    Westinghouse Savannah River Company is implementing productivity improvement concepts into the Waste Minimization Program by focusing on the positive initiatives taken to reduce waste generation at the Savannah River Site. Previous performance measures, based only on waste generation rates, proved to be an ineffective metric for measuring performance and promoting continuous improvements within the Program. Impacts of mission changes and non-routine operations impeded development of baseline waste generation rates and often negated waste generation trending reports. A system was developed to quantify, document and track innovative activities that impact waste volume and radioactivity/toxicity reductions. This system coupled with Management-driven waste disposal avoidance goals is proving to be a powerful tool to promote waste minimization awareness and the implementation of waste reduction initiatives. Measurement of waste not generated, in addition to waste generated, increases the credibility of the Waste Minimization Program, improves sharing of success stories, and supports development of regulatory and management reports

  20. Technology applications for radioactive waste minimization

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1994-01-01

    The nuclear power industry has achieved one of the most successful examples of waste minimization. The annual volume of low-level radioactive waste shipped for disposal per reactor has decreased to approximately one-fifth the volume about a decade ago. In addition, the curie content of the total waste shipped for disposal has decreased. This paper will discuss the regulatory drivers and economic factors for waste minimization and describe the application of technologies for achieving waste minimization for low-level radioactive waste with examples from the nuclear power industry

  1. Waste minimization at Chalk River Laboratories

    International Nuclear Information System (INIS)

    Kranz, P.; Wong, P.C.F.

    2011-01-01

    Waste minimization supports Atomic Energy of Canada Limited (AECL) Environment Policy with regard to pollution prevention and has positive impacts on the environment, human health and safety, and economy. In accordance with the principle of pollution prevention, the quantities and degree of hazard of wastes requiring storage or disposition at facilities within or external to AECL sites shall be minimized, following the principles of Prevent, Reduce, Reuse, and Recycle, to the extent practical. Waste minimization is an important element in the Waste Management Program. The Waste Management Program has implemented various initiatives for waste minimization since 2007. The key initiatives have focused on waste reduction, segregation and recycling, and included: 1) developed waste minimization requirements and recycling procedure to establish the framework for applying the Waste Minimization Hierarchy; 2) performed waste minimization assessments for the facilities, which generate significant amounts of waste, to identify the opportunities for waste reduction and assist the waste generators to develop waste reduction targets and action plans to achieve the targets; 3) implemented the colour-coded, standardized waste and recycling containers to enhance waste segregation; 4) established partnership with external agents for recycling; 5) extended the likely clean waste and recyclables collection to selected active areas; 6) provided on-going communications to promote waste reduction and increase awareness for recycling; and 7) continually monitored performance, with respect to waste minimization, to identify opportunities for improvement and to communicate these improvements. After implementation of waste minimization initiatives at CRL, the solid waste volume generated from routine operations at CRL has significantly decreased, while the amount of recyclables diverted from the onsite landfill has significantly increased since 2007. The overall refuse volume generated at

  2. Waste minimization at Chalk River Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Kranz, P.; Wong, P.C.F. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2011-07-01

    Waste minimization supports Atomic Energy of Canada Limited (AECL) Environment Policy with regard to pollution prevention and has positive impacts on the environment, human health and safety, and economy. In accordance with the principle of pollution prevention, the quantities and degree of hazard of wastes requiring storage or disposition at facilities within or external to AECL sites shall be minimized, following the principles of Prevent, Reduce, Reuse, and Recycle, to the extent practical. Waste minimization is an important element in the Waste Management Program. The Waste Management Program has implemented various initiatives for waste minimization since 2007. The key initiatives have focused on waste reduction, segregation and recycling, and included: 1) developed waste minimization requirements and recycling procedure to establish the framework for applying the Waste Minimization Hierarchy; 2) performed waste minimization assessments for the facilities, which generate significant amounts of waste, to identify the opportunities for waste reduction and assist the waste generators to develop waste reduction targets and action plans to achieve the targets; 3) implemented the colour-coded, standardized waste and recycling containers to enhance waste segregation; 4) established partnership with external agents for recycling; 5) extended the likely clean waste and recyclables collection to selected active areas; 6) provided on-going communications to promote waste reduction and increase awareness for recycling; and 7) continually monitored performance, with respect to waste minimization, to identify opportunities for improvement and to communicate these improvements. After implementation of waste minimization initiatives at CRL, the solid waste volume generated from routine operations at CRL has significantly decreased, while the amount of recyclables diverted from the onsite landfill has significantly increased since 2007. The overall refuse volume generated at

  3. Waste minimization applications at a remediation site

    International Nuclear Information System (INIS)

    Allmon, L.A.

    1995-01-01

    The Fernald Environmental Management Project (FEMP) owned by the Department of Energy was used for the processing of uranium. In 1989 Fernald suspended production of uranium metals and was placed on the National Priorities List (NPL). The site's mission has changed from one of production to environmental restoration. Many groups necessary for producing a product were deemed irrelevant for remediation work, including Waste Minimization. Waste Minimization does not readily appear to be applicable to remediation work. Environmental remediation is designed to correct adverse impacts to the environment from past operations and generates significant amounts of waste requiring management. The premise of pollution prevention is to avoid waste generation, thus remediation is in direct conflict with this premise. Although greater amounts of waste will be generated during environmental remediation, treatment capacities are not always available and disposal is becoming more difficult and costly. This creates the need for pollution prevention and waste minimization. Applying waste minimization principles at a remediation site is an enormous challenge. If the remediation site is also radiologically contaminated it is even a bigger challenge. Innovative techniques and ideas must be utilized to achieve reductions in the amount of waste that must be managed or dispositioned. At Fernald the waste minimization paradigm was shifted from focusing efforts on source reduction to focusing efforts on recycle/reuse by inverting the EPA waste management hierarchy. A fundamental difference at remediation sites is that source reduction has limited applicability to legacy wastes but can be applied successfully on secondary waste generation. The bulk of measurable waste reduction will be achieved by the recycle/reuse of primary wastes and by segregation and decontamination of secondary wastestreams. Each effort must be measured in terms of being economically and ecologically beneficial

  4. Separations: The path to waste minimization

    International Nuclear Information System (INIS)

    Bell, J.T.

    1992-01-01

    Waste materials usually are composed of large amounts of innocuous and frequently useful components mixed with lesser amounts of one or more hazardous components. The ultimate path to waste minimization is the separation of the lesser quantities of hazardous components from the innocuous components, and then recycle the useful components. This vision is so simple that everyone would be expected to properly manage waste. Several parameters interfere with this proper waste management, which encourages the open-quotes sweep it under the rugclose quotes or the open-quotes bury it allclose quotes attitudes, both of which delay and complicate proper waste management. The two primary parameters that interfere with proper waste management are: economics drives a process to a product without concerns of waste minimization, and emergency needs for immediate production of a product usually delays proper waste management. A third parameter in recent years is also interfering with proper waste management: quick relief of waste insults to political and public perceptions is promoting the open-quotes bury it allclose quotes attitude. A fourth parameter can promote better waste management for any scenario that suffers either or all of the first three parameters: separations technology can minimize wastes when the application of this technology is not voided by influence of the first three parameters. The US Department of Energy's management of nuclear waste has been seriously affected by the above four parameters. This paper includes several points about how the generation and management of DOE wastes have been, and continue to be, affected by these parameters. Particular separations technologies for minimizing the DOE wastes that must be stored for long periods are highlighted

  5. Assessment of LANL waste minimization plan

    International Nuclear Information System (INIS)

    Davis, K.D.; McNair, D.A.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The objective of this report is to evaluate the Los Alamos National Laboratory (LANL) Waste Minimization Plan to determine if it meets applicable internal (DOE) and regulatory requirements. The intent of the effort is to assess the higher level elements of the documentation to determine if they have been addressed rather than the detailed mechanics of the program's implementation. The requirement for a Waste Minimization Plan is based in several DOE Orders as well as environmental laws and regulations. Table 2-1 provides a list of the major documents or regulations that require waste minimization efforts. The table also summarizes the applicable requirements

  6. Pollution Prevention/Waste Minimization

    International Nuclear Information System (INIS)

    Fowler, Kimberly M.; Hyman, Marvin H.

    2002-01-01

    This chapter offers pollution prevention techniques for design, industrial process, maintenance, and environmental remediation activities. It provides examples of waste reduction, tools for identifying pollution prevention opportunities, and ways of calculating the payback or return on investment associated with the opportunities

  7. Prevention and minimization of waste production

    International Nuclear Information System (INIS)

    Noynaert, L.

    1998-01-01

    The main objective of the program Prevention and Minimization of Waste Production at the Belgian Nuclear Research Centre SCK/CEN is to contribute to reducing the volume and costs of nuclear waste. In addition, it aims to provide reliable data and models to the design engineers with a view to determining the final plant characteristics. Main activities in 1997 are described

  8. The OTD Robotics Waste Minimization Program

    International Nuclear Information System (INIS)

    Couture, S.A.

    1992-04-01

    The danger to human health and safety posed by exposure to transuranic (TRU) and Pu contaminated materials necessitates remote processing in confined environments. Currently these operations are carried out in gloveboxes and hot-cells by human operators using lead- lined gloves or teleoperated manipulators. Protective clothing worn by operators during gloved operations has contributed significantly to the waste problems currently facing site remediators. The DOE Environmental Restoration and Waste Management (ER/WM) Program is in the process of developing and demonstrating technologies to assist in the remediation of sites that have accumulated wastes generated using these processes over the past five decades. Recognizing that continued use of existing production, recovery and waste treatment systems will compound the remediation problem, DOE has made a commitment to waste minimization. To reduce waste generation during weapons production and waste processing operations, automated processes are being developed and demonstrated for use in future DOE processing facilities as part of OTD's Robotics Technology Development Program. These technologies are currently being applied to pyrochemical processing systems to demonstrate conversion of plutonium oxide to metal. However, these technologies are expected to have applications in a variety of waste processing systems including those used to treat high-level tank wastes, buried wastes requiring remote processing, mixed wastes, and unknown hazardous materials. In addition to reducing the future waste burden of DOE, automated processes are an effective way to comply with existing and anticipated federal, state, and local regulations related to personal health and safety and the health of the environment

  9. Plasma cleaning for waste minimization

    Energy Technology Data Exchange (ETDEWEB)

    Ward, P.P.

    1993-07-01

    Although plasma cleaning is a recognized substitute for solvent cleaning in removing organic contaminants, some universal problems in plasma cleaning processes prevent wider use of plasma techniques. Lack of understanding of the fundamental mechanisms of the process, unreliable endpoint detection techniques, and slow process times make plasma cleaning processes less than desirable. Our approach to address these plasma cleaning problems is described. A comparison of plasma cleaning rates of oxygen and oxygen/sulfur hexafluoride gases shows that fluorine-containing plasmas can enhance etch rates by 400% over oxygen alone. A discussion of various endpoint indication techniques is discussed and compared for application suitability. Work toward a plasma cleaning database is discussed. In addition to the global problems of plasma cleaning, an experiment where the specific mixed-waste problem of removal of machine oils from radioactive scrap metal is discussed.

  10. Minimization and segregation of radioactive wastes

    International Nuclear Information System (INIS)

    1992-07-01

    The report will serve as one of a series of technical manuals providing reference material and direct know-how to staff in radioisotope user establishments and research centres in Member States without nuclear power and the associated range of complex waste management operations. Considerations are limited to the minimization and segregation of wastes, these being initial steps on which the efficiency of the whole waste management system depends. The minimization and segregation operations are examined in the context of the restricted quantities and predominantly shorter lived activities of wastes from nuclear research, production and usage of radioisotopes. Liquid and solid wastes only are considered in the report. Gaseous waste minimization and treatment are specialized subjects and are not examined in this document. Gaseous effluent treatment in facilities handling low and intermediate level radioactive materials has been already the subject of a detailed IAEA report. Management of spent sealed sources has specifically been covered in a previous manual. Conditioned sealed sources must be taken into account in segregation arrangements for interim storage and disposal where there are exceptional long lived highly radiotoxic isotopes, particularly radium or americium. These are unlikely ever to be suitable for shallow land burial along with the remaining wastes. 30 refs, 5 figs, 8 tabs

  11. Commercial radioactive waste minimization program development guidance

    International Nuclear Information System (INIS)

    Fischer, D.K.

    1991-01-01

    This document is one of two prepared by the EG ampersand G Idaho, Inc., Waste Management Technical Support Program Group, National Low-Level Waste Management Program Unit. One of several Department of Energy responsibilities stated in the Amendments Act of 1985 is to provide technical assistance to compact regions Host States, and nonmember States (to the extent provided in appropriations acts) in establishing waste minimization program plans. Technical assistance includes, among other things, the development of technical guidelines for volume reduction options. Pursuant to this defined responsibility, the Department of Energy (through EG ampersand G Idaho, Inc.) has prepared this report, which includes guidance on defining a program, State/compact commission participation, and waste minimization program plans

  12. Prevention and Minimization of Waste Production

    International Nuclear Information System (INIS)

    Noynaert, L.; Bruggeman, A.; Rahier, A.

    1998-01-01

    The general objectives of SCK-CEN's programme on the prevention and minimization of waste production are to contribute to reducing volumes and cost of radioactive waste. It also aims tro provide reliable data and models to the design engineers with a view to determining the final plant characteristics. In the long term, these objectives will be extended to other nuclear applications. Progress and achievements in 1997 are summarised

  13. Minimization of radioactive solid wastes from uranium mining and metallurgy

    International Nuclear Information System (INIS)

    Zhang Xueli; Xu Lechang; Wei Guangzhi; Gao Jie; Wang Erqi

    2010-01-01

    The concept and contents of radioactive waste minimization are introduced. The principle of radioactive waste minimization involving administration optimization, source reduction, recycling and reuse as well as volume reduction are discussed. The strategies and methods to minimize radioactive solid wastes from uranium mining and metallurgy are summarized. In addition, the benefit from its application of radioactive waste minimization is analyzed. Prospects for the research on radioactive so-lid waste minimization are made in the end. (authors)

  14. Waste minimization - Hanford's strategy for sustainability

    International Nuclear Information System (INIS)

    Merry, D.S.

    1998-01-01

    The Hanford Site cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single-shell storage tanks, treating waste stored in 28 double-shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored onsite, removing thousands of structures, and dealing with significant solid waste, groundwater, and land restoration issues. The Pollution Prevention/Waste Minimization (P2/WMin) Program supports the Hanford Site mission to safely clean up and manage legacy waste and to develop and deploy science and technology in many ways. Once such way is through implementing and documenting over 231 waste reduction projects during the past five years, resulting in over $93 million in cost savings/avoidances. These savings/avoidances allowed other high priority cleanup work to be performed. Another way is by exceeding the Secretary of Energy's waste reduction goals over two years ahead of schedule, thus reducing the amount of waste to be stored, treated and disposed. Six key elements are the foundation for these sustained P2/WMin results

  15. Lawrence Livermore National Laboratory (LLNL) Experimental Test Site (Site 300) Salinity Evaluation and Minimization Plan for Cooling Towers and Mechanical Equipment Discharges

    Energy Technology Data Exchange (ETDEWEB)

    Daily III, W D

    2010-02-24

    This document was created to comply with the Central Valley Regional Water Quality Control Board (CVRWQCB) Waste Discharge Requirement (Order No. 98-148). This order established new requirements to assess the effect of and effort required to reduce salts in process water discharged to the subsurface. This includes the review of technical, operational, and management options available to reduce total dissolved solids (TDS) concentrations in cooling tower and mechanical equipment water discharges at Lawrence Livermore National Laboratory's (LLNL's) Experimental Test Site (Site 300) facility. It was observed that for the six cooling towers currently in operation, the total volume of groundwater used as make up water is about 27 gallons per minute and the discharge to the subsurface via percolation pits is 13 gallons per minute. The extracted groundwater has a TDS concentration of 700 mg/L. The cooling tower discharge concentrations range from 700 to 1,400 mg/L. There is also a small volume of mechanical equipment effluent being discharged to percolation pits, with a TDS range from 400 to 3,300 mg/L. The cooling towers and mechanical equipment are maintained and operated in a satisfactory manner. No major leaks were identified. Currently, there are no re-use options being employed. Several approaches known to reduce the blow down flow rate and/or TDS concentration being discharged to the percolation pits and septic systems were reviewed for technical feasibility and cost efficiency. These options range from efforts as simple as eliminating leaks to implementing advanced and innovative treatment methods. The various options considered, and their anticipated effect on water consumption, discharge volumes, and reduced concentrations are listed and compared in this report. Based on the assessment, it was recommended that there is enough variability in equipment usage, chemistry, flow rate, and discharge configurations that each discharge location at Site 300

  16. Lawrence Livermore National Laboratory (LLNL) Experimental Test Site (Site 300) Salinity Evaluation and Minimization Plan for Cooling Towers and Mechanical Equipment Discharges

    International Nuclear Information System (INIS)

    Daily, W.D. III

    2010-01-01

    This document was created to comply with the Central Valley Regional Water Quality Control Board (CVRWQCB) Waste Discharge Requirement (Order No. 98-148). This order established new requirements to assess the effect of and effort required to reduce salts in process water discharged to the subsurface. This includes the review of technical, operational, and management options available to reduce total dissolved solids (TDS) concentrations in cooling tower and mechanical equipment water discharges at Lawrence Livermore National Laboratory's (LLNL's) Experimental Test Site (Site 300) facility. It was observed that for the six cooling towers currently in operation, the total volume of groundwater used as make up water is about 27 gallons per minute and the discharge to the subsurface via percolation pits is 13 gallons per minute. The extracted groundwater has a TDS concentration of 700 mg/L. The cooling tower discharge concentrations range from 700 to 1,400 mg/L. There is also a small volume of mechanical equipment effluent being discharged to percolation pits, with a TDS range from 400 to 3,300 mg/L. The cooling towers and mechanical equipment are maintained and operated in a satisfactory manner. No major leaks were identified. Currently, there are no re-use options being employed. Several approaches known to reduce the blow down flow rate and/or TDS concentration being discharged to the percolation pits and septic systems were reviewed for technical feasibility and cost efficiency. These options range from efforts as simple as eliminating leaks to implementing advanced and innovative treatment methods. The various options considered, and their anticipated effect on water consumption, discharge volumes, and reduced concentrations are listed and compared in this report. Based on the assessment, it was recommended that there is enough variability in equipment usage, chemistry, flow rate, and discharge configurations that each discharge location at Site 300 should be

  17. National Institutes of Health: Mixed waste minimization and treatment

    International Nuclear Information System (INIS)

    1995-08-01

    The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy's National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified

  18. National Institutes of Health: Mixed waste minimization and treatment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy`s National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified.

  19. Waste minimization and pollution prevention awareness plan

    International Nuclear Information System (INIS)

    1994-08-01

    The primary mission of DOE/NV is to manage and operate the Nevada Test Site (NTS) and other designated test locations, within and outside the United States; provide facilities and services to DOE and non-DOE NTS users; and plan. coordinate, and execute nuclear weapons tests and related test activities. DOE/NV also: (a) Supports operations under interagency agreements pertaining to tests, emergencies, and related functions/activities, (b) Plans, coordinates, and executes environmental restoration, (c) Provides support to the Yucca Mountain Site Characterization Project Office in conjunction with DOE/HQ oversight, (d) Manages the Radioactive Waste Management Sites (RWMS) for disposal of low-level and mixed wastes received from the NTS and off-site generators, and (e) Implements waste minimization programs to reduce the amount of hazardous, mixed, radioactive, and nonhazardous solid waste that is generated and disposed The NTS, which is the primary facility controlled by DOE/NV, occupies 1,350 square miles of restricted-access, federally-owned land located in Nye County in Southern Nevada. The NTS is located in a sparsely populated area, approximately 65 miles northwest of Las Vegas, Nevada

  20. Hazardous waste minimization report for CY 1986

    International Nuclear Information System (INIS)

    Kendrick, C.M.

    1990-12-01

    Oak Ridge National Laboratory (ORNL) is a multipurpose research and development facility. Its primary role is the support of energy technology through applied research and engineering development and scientific research in basic and physical sciences. ORNL also is a valuable resource in the solution of problems of national importance, such as nuclear and chemical waste management. In addition, useful radioactive and stable isotopes which are unavailable from the private sector are produced at ORNL. As a result of these activities, hazardous, radioactive, and mixed wastes are generated at ORNL. A formal hazardous waste minimization program for ORNL was launched in mid 1985 in response to the requirements of Section 3002 of the Resource Conservation and Recovery Act (RCRA). During 1986, a task plan was developed. The six major tasks include: planning and implementation of a laboratory-wide chemical inventory and the subsequent distribution, treatment, storage, and/or disposal (TSD) of unneeded chemicals; establishment and implementation of a distribution system for surplus chemicals to other (internal and external) organizations; training and communication functions necessary to inform and motivate laboratory personnel; evaluation of current procurement and tracking systems for hazardous materials and recommendation and implementation of improvements; systematic review of applicable current and proposed ORNL procedures and ongoing and proposed activities for waste volume and/or toxicity reduction potential; and establishment of criteria by which to measure progress and reporting of significant achievements. 8 refs., 1 fig., 5 tabs

  1. Waste Minimization via Radiological Hazard Reduction

    International Nuclear Information System (INIS)

    Stone, K.A.; Coffield, T.; Hooker, K.L.

    1998-01-01

    The Savannah River Site (SRS), a 803 km 2 U.S. Department of Energy (DOE) facility in south-western South Carolina, incorporates pollution prevention as a fundamental component of its Environmental Management System. A comprehensive pollution prevention program was implemented as part of an overall business strategy to reduce waste generation and pollution releases, minimize environmental impacts, and to reduce future waste management and pollution control costs. In fiscal years 1995 through 1997, the Site focused on implementing specific waste reduction initiatives identified while benchmarking industry best practices. These efforts resulted in greater than $25 million in documented cost avoidance. While these results have been dramatic to date, the Site is further challenged to maximize resource utilization and deploy new technologies and practices to achieve further waste reductions. The Site has elected to target a site-wide reduction of contaminated work spaces in fiscal year 1998 as the primary source reduction initiative. Over 120,900 m 2 of radiologically contaminated work areas (approximately 600 separate inside areas) exist at SRS. Reduction of these areas reduces future waste generation, minimizes worker exposure, and reduces surveillance and maintenance costs. This is a major focus of the Site's As Low As Reasonably Achievable (ALARA) program by reducing sources of worker exposure. The basis for this approach was demonstrated during 1997 as part of a successful Enhanced Work Planning pilot conducted at several specific contamination areas at SRS. An economic-based prioritization process was utilized to develop a model for prioritizing areas to reclaim. In the H-Canyon Separation facility, over 3,900 m 2 of potentially contaminated area was rolled back to a Radiation Buffer Area. The facility estimated nearly 420 m 3 of low level radioactive waste will be avoided each year, and overall cost savings and productivity gains will reach approximately $1

  2. Waste Minimization Study on Pyrochemical Reprocessing Processes

    International Nuclear Information System (INIS)

    Boussier, H.; Conocar, O.; Lacquement, J.

    2006-01-01

    ' new block diagram allowing internal solvent recycling, and self eliminating reactants. This new flowsheet minimizes the quantity of inactive inlet flows that would have inevitably to be incorporated in a final waste form. The study identifies all knowledge gaps to be filled and suggest some possible R and D issues to confirm or infirm the feasibility of the proposed process fittings. (authors)

  3. Summary of International Waste Management Programs (LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW)

    Energy Technology Data Exchange (ETDEWEB)

    Greenberg, Harris R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Blink, James A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Halsey, William G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sutton, Mark [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2011-08-11

    The Used Fuel Disposition Campaign (UFDC) within the Department of Energy’s Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation’s spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. This Lessons Learned task is part of a multi-laboratory effort, with this LLNL report providing input to a Level 3 SNL milestone (System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW). The work package number is: FTLL11UF0328; the work package title is: Technical Bases / Lessons Learned; the milestone number is: M41UF032802; and the milestone title is: “LLNL Input to SNL L3 MS: System-Wide Integration and Site Selection Concepts for Future Disposition Options for HLW”. The system-wide integration effort will integrate all aspects of waste management and disposal, integrating the waste generators, interim storage, transportation, and ultimate disposal at a repository site. The review of international experience in these areas is required to support future studies that address all of these components in an integrated manner. Note that this report is a snapshot of nuclear power infrastructure and international waste management programs that is current as of August 2011, with one notable exception. No attempt has been made to discuss the currently evolving world-wide response to the tragic consequences of the earthquake and tsunami that devastated Japan on March 11, 2011, leaving more than 15,000 people dead and more than 8,000 people missing, and severely damaging the Fukushima Daiichi nuclear power complex. Continuing efforts in FY 2012 will update the data, and summarize it in an Excel spreadsheet for easy comparison and assist in the knowledge management of the study cases.

  4. Status of LLNL granite projects

    International Nuclear Information System (INIS)

    Ramspott, L.D.

    1980-01-01

    The status of LLNL Projects dealing with nuclear waste disposal in granitic rocks is reviewed. This review covers work done subsequent to the June 1979 Workshop on Thermomechanical Modeling for a Hardrock Waste Repository and is prepared for the July 1980 Workshop on Thermomechanical-Hydrochemical Modeling for a Hardrock Waste Repository. Topics reviewed include laboratory determination of thermal, mechanical, and transport properties of rocks at conditions simulating a deep geologic repository, and field testing at the Climax granitic stock at the USDOE Nevada Test Site

  5. Experience with the EPA manual for waste minimization opportunity assessments

    International Nuclear Information System (INIS)

    Bridges, J.S.

    1990-01-01

    The EPA Waste Minimization Opportunity Assessment Manual (EPA/625/788/003) was published to assist those responsible for managing waste minimization activities at the waste generating facility and at corporate levels. The Manual sets forth a procedure that incorporates technical and managerial principles and motivates people to develop and implement pollution prevention concepts and ideas. Environmental management has increasingly become one of cooperative endeavor whereby whether in government, industry, or other forms of enterprise, the effectiveness with whirl, people work together toward the attainment of a clean environment is largely determined by the ability of those who hold managerial position. This paper offers a description of the EPA Waste Minimization Opportunity Assessment Manual procedure which supports the waste minimization assessment as a systematic planned procedure with the objective of identifying ways to reduce or eliminate waste generation. The Manual is a management tool that blends science and management principles. The practice of managing waste minimization/pollution prevention makes use of the underlying organized science and engineering knowledge and applies it in the light of realities to gain a desired, practical result. The early stages of EPA's Pollution Prevention Research Program centered on the development of the Manual and its use at a number of facilities within the private and public sectors. This paper identifies a number of case studies and waste minimization opportunity assessment reports that demonstrate the value of using the Manual's approach. Several industry-specific waste minimization assessment manuals have resulted from the Manual's generic approach to waste minimization. There were some modifications to the Manual's generic approach when the waste stream has been other than industrial hazardous waste

  6. The waste minimization program at the Feed Materials Production Center

    International Nuclear Information System (INIS)

    Blasdel, J.E.; Crotzer, M.E.; Gardner, R.L.; Kato, T.R.; Spradlin, C.N.

    1987-01-01

    A waste minimization program is being implemented at the Feed Materials Production Center to reduce the generation of uranium-contaminated wastes and to comply with existing and forthcoming regulations. Procedures and plans are described which deal with process and non-process trash, contaminated wood and metals, used metal drums, and major process wastes such as contaminated magnesium fluoride and neutralized raffinate. Waste minimization techniques used include segregation, source reduction, volume reduction, material substitution and waste/product recycle. The importance of training, communication, and incentives is also covered. 5 refs., 11 figs

  7. The Construction Solid Waste Minimization Practices among Malaysian Contractors

    Directory of Open Access Journals (Sweden)

    Che Ahmad A.

    2014-01-01

    Full Text Available The function of minimization of construction solid waste is to reduce or eliminates the adverse impacts on the environment and to human health. Due to the increase of population that leads to rapid development, there are possibilities of construction solid waste to be increased shortly from the construction works, demolition or renovation works. Materials such as wood, concrete, paint, brick, roofing, tiles, plastic and any other materials would contribute problem involving construction solid waste. Therefore, the proper waste minimization is needed to control the quantity of construction solid waste produced. This paper identifies the type of construction solid waste produced and discusses the waste minimization practice by the contractors at construction sites in Selangor, Kuala Lumpur and Putrajaya, Malaysia.

  8. 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

  9. Foam is a decon waste minimization tool

    International Nuclear Information System (INIS)

    Peterson, K.D.; McGlynn, J.F.; Rankin, W.N.

    1991-01-01

    The use of foam in decontamination operations offers significant reductions in waste generation. Initial use has confirmed its effectiveness. Issues being resolved at Savannah River Site (SRS) include compatibility of foam generating solutions with decontamination solutions, waste disposal, and operational safety

  10. 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

  11. 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.

  12. Safety control and minimization of radioactive wastes

    International Nuclear Information System (INIS)

    Wang Jinming; Rong Feng; Li Jinyan; Wang Xin

    2010-01-01

    Compared with the developed countries, the safety control and minimization of the radwastes in China are under-developed. The research of measures for the safety control and minimization of the radwastes is very important for the safety control of the radwastes, and the reduction of the treatment and disposal cost and environment radiation hazards. This paper has systematically discussed the safety control and the minimization of the radwastes produced in the nuclear fuel circulation, nuclear technology applications and the process of decommission of nuclear facilities, and has provided some measures and methods for the safety control and minimization of the radwastes. (authors)

  13. 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.

  14. Hazardous Waste Minimization Assessment: Fort Campbell, Kentucky

    Science.gov (United States)

    1991-03-01

    gal/h -- $8,250 (solvents: chlorinated and $8,600 fluorinated ) 114 Table 39 Aqueous Waste Volume Reduction Equipment Suppliers* Supplier Model Capacity...heavy chloride/hydrochloric acid metal solutions (chromium), nitric acid (zinc, magnesium) Printing (Ink) pigments, dyes, varnish , titanium oxide, iron...lacquers, epoxy. aLkyds. acrylics) :inshing Varnish . shellac, lacquer 13001 Waste flammable liquid. NOS Flammable liquid UN1993 Preserving Creosote

  15. Trim waste minimization at the Pinellas Plant

    International Nuclear Information System (INIS)

    DeLaneuville, D.

    1992-01-01

    Bacteria counts and several methods of slowing bacterial growth in machine trim coolant are suggested to reduce the frequency of coolant replacement without risking employee health or the longevity of the product or machinery. On-site treatment and disposal of waste trim are recommended to further reduce waste volume. This paper discusses the benefits of these efforts, including projected cost savings based on partial implementation at the Department of Energy's Pinellas Plant

  16. Low-level radioactive waste minimization for health care institutions

    International Nuclear Information System (INIS)

    Williams, G.

    1990-01-01

    In recent years medical waste has been the subject of considerable public and governmental attention. This has been, in part, due to the media's attraction to unfortunate instances of environmental pollution caused by hazardous and medical wastes. While a considerable amount of information is currently available on the treatment and disposal practices for hazardous wastes, a shortfall of information exists on the subject of medical wastes. Such wastes are generated by various health care institutions. Medical waste is a wide and all encompassing term which refers to a variety of wastes. This presentation addresses medical low-level (LLW) radioactive waste; its generation, recovery and handling. The development of generic waste minimization models and greater use of alternative technologies are part of the discussion

  17. Waste Minimization Policy at the Romanian Nuclear Power Plant

    International Nuclear Information System (INIS)

    Andrei, V.; Daian, I.

    2002-01-01

    The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP

  18. Minimizing generator liability while disposing hazardous waste

    International Nuclear Information System (INIS)

    Canter, L.W.; Lahlou, M.; Pendurthi, R.P.

    1991-01-01

    Potential liabilities associated with hazardous waste disposal are related to waste properties, disposal practices and the potential threat to people and the environment in case of a pollutant release. Based on various regulations, these liabilities are enforceable and longstanding. A methodology which can help hazardous waste generators select a commercial disposal facility with a relatively low risk of potential liability is described in this paper. The methodology has two parts. The first part has 8 categories encompassing 30 factors common to all facilities, and the second part includes one category dealing with 5 factors on specific wastes and treatment/disposal technologies. This two-part evaluation feature enables the user to adapt the methodology to any type of waste disposal. In determining the scores for the factors used in the evaluation. an unranked paired comparison technique with slight modifications was used to weight the relative importance of the individual factors. In the methodology it is possible for the user to redefine the factors and change the scoring system. To make the methodology more efficient, a user-friendly computer program has been developed; the computer program is written so that desired changes in the methodology can be readily implemented

  19. Waste minimization for land-based drilling operations

    International Nuclear Information System (INIS)

    Thurber, N.E.

    1992-01-01

    This paper discusses engineering variables that should be addressed to minimize waste-toxicity and generation while drilling land-based wells. Proper balance of these variables provides both operational and environmental benefits

  20. Waste minimization for land-based drilling operations

    International Nuclear Information System (INIS)

    Thurber, N.E.

    1991-01-01

    This paper discusses many of the engineering variables that should be addressed to minimize waste toxicity and generation during the drilling of land-based wells. Proper balance of these variables suggests both operational and environmental benefits

  1. Secondary waste minimization in analytical methods

    International Nuclear Information System (INIS)

    Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S.; Schilling, J.B.

    1995-01-01

    The characterization phase of site remediation is an important and costly part of the process. Because toxic solvents and other hazardous materials are used in common analytical methods, characterization is also a source of new waste, including mixed waste. Alternative analytical methods can reduce the volume or form of hazardous waste produced either in the sample preparation step or in the measurement step. The authors are examining alternative methods in the areas of inorganic, radiological, and organic analysis. For determining inorganic constituents, alternative methods were studied for sample introduction into inductively coupled plasma spectrometers. Figures of merit for the alternative methods, as well as their associated waste volumes, were compared with the conventional approaches. In the radiological area, the authors are comparing conventional methods for gross α/β measurements of soil samples to an alternative method that uses high-pressure microwave dissolution. For determination of organic constituents, microwave-assisted extraction was studied for RCRA regulated semivolatile organics in a variety of solid matrices, including spiked samples in blank soil; polynuclear aromatic hydrocarbons in soils, sludges, and sediments; and semivolatile organics in soil. Extraction efficiencies were determined under varying conditions of time, temperature, microwave power, moisture content, and extraction solvent. Solvent usage was cut from the 300 mL used in conventional extraction methods to about 30 mL. Extraction results varied from one matrix to another. In most cases, the microwave-assisted extraction technique was as efficient as the more common Soxhlet or sonication extraction techniques

  2. Waste minimization in a petrochemical company

    Energy Technology Data Exchange (ETDEWEB)

    Anan, Marcelo [Oxiteno S.A., Industria e Comercio, Sao Paulo, SP (Brazil)

    1993-12-31

    A way to manage industrial effluents consists in reducing their generation or treating them when elimination or minimization is economically unachievable. This work aims to present the modifications adopted in a petrochemical plant to adequate and, or, reduce the generation of industrial effluent. 8 refs., 3 figs.

  3. Waste minimization in a petrochemical company

    Energy Technology Data Exchange (ETDEWEB)

    Anan, Marcelo [Oxiteno S.A., Industria e Comercio, Sao Paulo, SP (Brazil)

    1994-12-31

    A way to manage industrial effluents consists in reducing their generation or treating them when elimination or minimization is economically unachievable. This work aims to present the modifications adopted in a petrochemical plant to adequate and, or, reduce the generation of industrial effluent. 8 refs., 3 figs.

  4. Minimization of waste from uranium purification, enrichment and fuel fabrication

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-10-01

    As any industry, nuclear industry generates a diverse range of waste which has to be managed in a safe manner to be acceptable to the public and the environment. The cost of waste management, the risks to the public and employees, and the detriment to the environment are dependent on the quantity and radioactive content of the waste generated. Waste minimization is a necessary activity needed to reduce the impact from nuclear fuel cycle operations and it is included in the national policy of some countries. In recognition of the importance of the subject, the IAEA has decided to review the current status of the work aimed at waste minimization in the nuclear fuel cycle. The waste minimization issues related to the back end of the nuclear fuel cycle are covered in Technical Reports Series No. 377 'Minimization of Radioactive Waste from Nuclear Power Plants and the Back End of the Nuclear Fuel Cycle' published in 1995. The present report deals with the front end of the nuclear fuel cycle, including existing options, approaches, developments and some specific considerations to be taken into account in decision making on waste minimization. It has been recognized that, in comparison with the back end of the nuclear fuel cycle, much less information is available, and this report should be considered as a first attempt to analyse waste minimization practices and opportunities in uranium purification, conversion, enrichment and fuel fabrication. Although mining and milling is an important part of the front end of the nuclear fuel cycle, these activities are excluded from consideration since relevant activities are covered in other IAEA publications.

  5. Minimization of waste from uranium purification, enrichment and fuel fabrication

    International Nuclear Information System (INIS)

    1999-10-01

    As any industry, nuclear industry generates a diverse range of waste which has to be managed in a safe manner to be acceptable to the public and the environment. The cost of waste management, the risks to the public and employees, and the detriment to the environment are dependent on the quantity and radioactive content of the waste generated. Waste minimization is a necessary activity needed to reduce the impact from nuclear fuel cycle operations and it is included in the national policy of some countries. In recognition of the importance of the subject, the IAEA has decided to review the current status of the work aimed at waste minimization in the nuclear fuel cycle. The waste minimization issues related to the back end of the nuclear fuel cycle are covered in Technical Reports Series No. 377 'Minimization of Radioactive Waste from Nuclear Power Plants and the Back End of the Nuclear Fuel Cycle' published in 1995. The present report deals with the front end of the nuclear fuel cycle, including existing options, approaches, developments and some specific considerations to be taken into account in decision making on waste minimization. It has been recognized that, in comparison with the back end of the nuclear fuel cycle, much less information is available, and this report should be considered as a first attempt to analyse waste minimization practices and opportunities in uranium purification, conversion, enrichment and fuel fabrication. Although mining and milling is an important part of the front end of the nuclear fuel cycle, these activities are excluded from consideration since relevant activities are covered in other IAEA publications

  6. Waste minimization through microexperimentation: Barriers to implementation

    International Nuclear Information System (INIS)

    Gatrone, R.C.

    1994-01-01

    In the past, synthesis of ligands and extractants for concentrating radwaste, often resulted in generating large amounts of hazardous wastes. Microexperimentation means handling amounts of organics on the scale of millimoles (10 -3 ) to micromoles (10 -6 ). More reliable analytical techniques allow one to obtain data nondestructively on the structure of a molecule on just a few milligrams of material. Obstacles to use of microscale techniques in laboratories include requirement of new, expensive equipment, and resistance of laboratory personnel to new techniques. It is emphasized that in the Argonne laboratory, of the 500 g of an extractant that was required in 1985, nearly 90% was ultimately discarded as waste after 5 years. DOE agreements and other Federal regulations require this be changed

  7. Waste minimization at a plutonium processing facility

    International Nuclear Information System (INIS)

    Pillay, K.K.S.

    1995-01-01

    As part of Los Alamos National Laboratory's (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management

  8. Cleaner production: Minimizing hazardous waste in Indonesia

    Energy Technology Data Exchange (ETDEWEB)

    Bratasida, D.L. [BAPEDAL, Jakarta (Indonesia)

    1996-12-31

    In the second long-term development plan, industry plays a significant role in economic growth. In Indonesia, industries grow very fast; such fast growth can adversely effect the environment. Exploitation of assets can mean depletion of natural resources and energy, which, if incorrectly managed, can endanger human life and the environment. The inefficient use of natural resources will accelerate their exhaustion and generate pollution, resulting in environmental damage and threats to economic development and human well being. In recent years, changes in the approach used to control pollution have been necessary because of the increasing seriousness of the problems. Initial environmental management strategies were based on a carrying capacity approach; the natural assimilative capacity accommodated the pollution load that was applied. The environmental management strategies adopted later included technologies applied to the end of the discharge point (so-called {open_quotes}end-of-pipe{close_quotes} treatments). Until now, environmental management strategies focused on end-of-pipe approaches that control pollutants after they are generated. These approaches concentrate on waste treatment and disposal to control pollution and environmental degradation. However, as industry develops, waste volumes continue to increase, thereby creating further environmental problems. In addition, the wastes produced tend to have more complex characteristics and are potentially more difficult to treat for a reasonable cost. There are often technical and financial obstacles to regulatory compliance if waste treatment is relied on as the only means of achieving environmental objectives. Consequently, the reactive end-of-pipe treatment approach has been changed to a proactive cleaner production approach. This approach is based on the concept of sustainable development and is designed to prevent pollution as well as to protect natural resources and the quality of the environment.

  9. Hanford Site waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    1994-05-01

    The Hanford Site WMin/P2 program is an organized, comprehensive, and continual effort to systematically reduce the quantity and toxicity of hazardous, radioactive, mixed, and sanitary wastes; conserve resources; and prevent or minimize pollutant releases to all environmental media from all Site activities. The Hanford Site WMin/P2 program plan reflects national and DOE waste minimization and pollution prevention goals and policies, and represents an ongoing effort to make WMin/P2 part of the Site operating philosophy. In accordance with these policies, a hierarchical approach to environmental management has been adopted and is applied to all types of polluting and waste generating activities. Pollution prevention and waste minimization through source reduction are first priority in the Hanford WMin/P2 program, followed by environmentally safe recycling. Treatment to reduce the quantity, toxicity, and/or mobility will be considered only when prevention or recycling are not possible or practical. Environmentally safe disposal is the last option

  10. Recent developments in the DOE Waste Minimization Pollution Prevention Program

    International Nuclear Information System (INIS)

    Hancock, J.K.

    1993-01-01

    The U.S. Department of Energy (DOE) is involved in a wide variety of research and development, remediation, and production activities at more than 100 sites throughout the United States. The wastes generated cover a diverse spectrum of sanitary, hazardous, and radioactive waste streams, including typical office environments, power generation facilities, laboratories, remediation sites, production facilities, and defense facilities. The DOE's initial waste minimization activities pre-date the Pollution Prevention Act of 1990 and focused on the defense program. Little emphasis was placed on nonproduction activities. In 1991 the Office of Waste Management Operations developed the Waste Minimization Division with the intention of coordinating and expanding the waste minimization pollution prevention approach to the entire complex. The diverse nature of DOE activities has led to several unique problems in addressing the needs of waste minimization and pollution prevention. The first problem is developing a program that addresses the geographical and institutional hurdles that exist; the second is developing a monitoring and reporting mechanism that one can use to assess the overall performance of the program

  11. Adoption of waste minimization technology to benefit electroplaters

    Energy Technology Data Exchange (ETDEWEB)

    Ching, E.M.K.; Li, C.P.H.; Yu, C.M.K. [Hong Kong Productivity Council, Kowloon (Hong Kong)

    1996-12-31

    Because of increasingly stringent environmental legislation and enhanced environmental awareness, electroplaters in Hong Kong are paying more heed to protect the environment. To comply with the array of environmental controls, electroplaters can no longer rely solely on the end-of-pipe approach as a means for abating their pollution problems under the particular local industrial environment. The preferred approach is to adopt waste minimization measures that yield both economic and environmental benefits. This paper gives an overview of electroplating activities in Hong Kong, highlights their characteristics, and describes the pollution problems associated with conventional electroplating operations. The constraints of using pollution control measures to achieve regulatory compliance are also discussed. Examples and case studies are given on some low-cost waste minimization techniques readily available to electroplaters, including dragout minimization and water conservation techniques. Recommendations are given as to how electroplaters can adopt and exercise waste minimization techniques in their operations. 1 tab.

  12. Advanced Purex process and waste minimization at La Hague

    International Nuclear Information System (INIS)

    Masson, H.; Nouguier, H.; Bernard, C.; Runge, S.

    1993-01-01

    After a brief recall of the different aspects of the commercial irradiated fuel reprocessing, this paper presents the achievements of the recently commissioned UP3 plant at La Hague. The advanced Purex process implemented with a total waste management results in important waste volume minimization, so that the total volume of high-level and transuranic waste is lower than what it would be in a once-through cycle. Moreover, further minimization is still possible, based on an improved waste management. Cogema has launched the necessary program, which will lead to an overall volume of HLW and TRU wastes of less than 1 m 3 /t by the end of the decade, the maximum possible activity being concentrated in the glass

  13. Minimization of rad waste production in NPP Dukovany

    International Nuclear Information System (INIS)

    Kulovany, J.

    2001-01-01

    A whole range of measures has been taken in the power plant in connection with the minimization of radioactive waste. It will lead to the set goals. The procedures that prevent possible endangering of the operation take precedence during introduction of the minimization measures. Further economically undemanding procedures are implemented that bring about minimization in an effective way. In accordance with the EMS principles it can be expected that the minimizing measures will be implemented also in areas where their greatest contribution will be for the environment

  14. Environmental Restoration Contractor Waste Minimization and Pollution Prevention Plan

    International Nuclear Information System (INIS)

    Lewis, R.A.

    1994-11-01

    The purpose of this plan is to establish the Environmental Restoration Contractor (ERC) Waste Minimization and Pollution Prevention (WMin/P2) Program and outline the activities and schedules that will be employed to reduce the quantity and toxicity of wastes generated as a result of restoration and remediation activities. It is intended to satisfy the US Department of Energy (DOE) and other legal requirements. As such, the Pollution Prevention Awareness program required by DOE Order 5400.1 is included with the Pollution Prevention Program. This plan is also intended to aid projects in meeting and documenting compliance with the various requirements for WMin/P2, and contains the policy, objectives, strategy, and support activities of the WMin/P2 program. The basic elements of the plan are pollution prevention goals, waste assessments of major waste streams, implementation of feasible waste minimization opportunities, and a process for reporting achievements. Various pollution prevention techniques will be implemented with the support of employee training and awareness programs to reduce waste and still meet applicable requirements. Information about the Hanford Site is in the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan

  15. Waste minimization/pollution prevention study of high-priority waste streams

    International Nuclear Information System (INIS)

    Ogle, R.B.

    1994-03-01

    Although waste minimization has been practiced by the Metals and Ceramics (M ampersand C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division's pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M ampersand C staff members empowered by the Division Director to study specific waste streams

  16. Waste minimization successes at McGuire Nuclear Station

    International Nuclear Information System (INIS)

    Correll, J.C.; Johnson, G.T.

    1995-01-01

    McGuire Nuclear Station is a two unit, 1125 MWe PWR located 25 miles north of Charlotte, North Carolina. It is a Westinghouse Ice Condenser plant that is owned and operated by Duke Power Company. At Duke Power, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation that we are making to become a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and disposed of our solid radioactive waste. With top-down management support, we have used team-based, formalized, problem solving methods and have implemented many successful waste minimization programs. Through these programs, we have dramatically increased employees close-quote awareness of the importance of waste minimization. As a result, we have been able to reduce both our burial volumes and our waste processing and disposal costs

  17. Treatment and minimization of heavy metal-containing wastes 1995

    International Nuclear Information System (INIS)

    Hager, J.P.; Mishra, B.; Litz, J.L.

    1995-01-01

    This symposium was held in conjunction with the 1995 Annual Meeting of the Minerals, Metals and Materials Society in Las Vegas, Nevada, February 12--16, 1995. The purpose of this meeting was to provide a forum for exchange of state-of-the-art information on treating and minimizing heavy metal-containing wastes. Papers were categorized under the following broad headings: aqueous processing; waste water treatment; thermal processing and stabilization; processing of fly ash, flue dusts, and slags; and processing of lead, mercury, and battery wastes. Individual papers have been processed separately for inclusion in the appropriate data bases

  18. Waste Minimization/Pollution Prevention Crosscut Plan, 1994

    International Nuclear Information System (INIS)

    1994-01-01

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

  19. LLNL 1981: technical horizons

    International Nuclear Information System (INIS)

    1981-07-01

    Research programs at LLNL for 1981 are described in broad terms. In his annual State of the Laboratory address, Director Roger Batzel projected a $481 million operating budget for fiscal year 1982, up nearly 13% from last year. In projects for the Department of Energy and the Department of Defense, the Laboratory applies its technical facilities and capabilities to nuclear weapons design and development and other areas of defense research that include inertial confinement fusion, nonnuclear ordnances, and particle-beam technology. LLNL is also applying its unique experience and capabilities to a variety of projects that will help the nation meet its energy needs in an environmentally acceptable manner. A sampling of recent achievements by LLNL support organizations indicates their diversity

  20. Mixed low-level waste minimization at Los Alamos

    International Nuclear Information System (INIS)

    Starke, T.P.

    1998-01-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL

  1. Mixed low-level waste minimization at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Starke, T.P.

    1998-12-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL.

  2. Health Physics and Waste Minimization Best Practices benchmarking study

    International Nuclear Information System (INIS)

    Levin, V.

    1995-01-01

    The Health Physics and Waste Minimization Best Practices project examines the usefulness of benchmarking as a tool for identifying health physics and waste minimization best practices for low-level solid radioactive waste (LLW) in the U.S. Department of Energy (DOE) complex. The goal of the project is to identify best practices from the nuclear power industry that will reduce the amount of LLW going to disposal in a cost-effective manner. An increase in worker efficiency and productivity is a secondary goal. These practices must be adaptable for implementation in the DOE complex. Once best practices are identified, ranked, and funded for implementation, a pilot implementation will be done at the Chemistry and Metallurgy Research (CMR) building at Los Alamos National Laboratory

  3. Low-level waste minimization at the Y-12 Plant

    Energy Technology Data Exchange (ETDEWEB)

    Koger, J. [Oak Ridge National Lab., TN (United States)

    1993-03-01

    The Y-12 Development Waste Minimization Program is used as a basis for defining new technologies and processes that produce minimum low-level wastes (hazardous, mixed, radioactive, and industrial) for the Y-12 Plant in the future and for Complex-21 and that aid in decontamination and decommissioning (D and D) efforts throughout the complex. In the past, the strategy at the Y-12 Plant was to treat the residues from the production processes using chemical treatment, incineration, compaction, and other technologies, which often generated copious quantities of additional wastes and, with the exception of highly valuable materials such as enriched uranium, incorporated very little recycle in the process. Recycle, in this context, is defined as material that is put back into the process before it enters a waste stream. Additionally, there are several new technology drivers that have recently emerged with the changing climate in the Nuclear Weapons Complex such as Complex 21 and D and D technologies and an increasing number of disassemblies. The hierarchies of concern in the waste minimization effort are source reduction, recycle capability, treatment simplicity, and final disposal difficulty with regard to Complex 21, disassembly efforts, D and D, and, to a lesser extent, weapons production. Source reduction can be achieved through substitution of hazardous substances for nonhazardous materials, and process changes that result in less generated waste.

  4. Molten salt treatment to minimize and optimize waste

    International Nuclear Information System (INIS)

    Gat, U.; Crosley, S.M.; Gay, R.L.

    1993-01-01

    A combination molten salt oxidizer (MSO) and molten salt reactor (MSR) is described for treatment of waste. The MSO is proposed for contained oxidization of organic hazardous waste, for reduction of mass and volume of dilute waste by evaporation of the water. The NTSO residue is to be treated to optimize the waste in terms of its composition, chemical form, mixture, concentration, encapsulation, shape, size, and configuration. Accumulations and storage are minimized, shipments are sized for low risk. Actinides, fissile material, and long-lived isotopes are separated and completely burned or transmuted in an MSR. The MSR requires no fuel element fabrication, accepts the materials as salts in arbitrarily small quantities enhancing safety, security, and overall acceptability

  5. The LLNL AMS facility

    International Nuclear Information System (INIS)

    Roberts, M.L.; Bench, G.S.; Brown, T.A.

    1996-05-01

    The AMS facility at Lawrence Livermore National Laboratory (LLNL) routinely measures the isotopes 3 H, 7 Be, 10 Be, 14 C, 26 Al, 36 Cl, 41 Ca, 59,63 Ni, and 129 I. During the past two years, over 30,000 research samples have been measured. Of these samples, approximately 30% were for 14 C bioscience tracer studies, 45% were 14 C samples for archaeology and the geosciences, and the other isotopes constitute the remaining 25%. During the past two years at LLNL, a significant amount of work has gone into the development of the Projectile X-ray AMS (PXAMS) technique. PXAMS uses induced characteristic x-rays to discriminate against competing atomic isobars. PXAMS has been most fully developed for 63 Ni but shows promise for the measurement of several other long lived isotopes. During the past year LLNL has also conducted an 129 I interlaboratory comparison exercise. Recent hardware changes at the LLNL AMS facility include the installation and testing of a new thermal emission ion source, a new multianode gas ionization detector for general AMS use, re-alignment of the vacuum tank of the first of the two magnets that make up the high energy spectrometer, and a new cryo-vacuum system for the AMS ion source. In addition, they have begun design studies and carried out tests for a new high-resolution injector and a new beamline for heavy element AMS

  6. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    International Nuclear Information System (INIS)

    1994-02-01

    This report is DOE's first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992

  7. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is DOE`s first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992.

  8. Using benchmarking to minimize common DOE waste streams. Volume 1, Methodology and liquid photographic waste

    Energy Technology Data Exchange (ETDEWEB)

    Levin, V.

    1994-04-01

    Finding innovative ways to reduce waste streams generated at Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE`s waste minimization efforts. This report examines the usefulness of benchmarking as a waste minimization tool, specifically regarding common waste streams at DOE sites. A team of process experts from a variety of sites, a project leader, and benchmarking consultants completed the project with management support provided by the Waste Minimization Division EM-352. Using a 12-step benchmarking process, the team examined current waste minimization processes for liquid photographic waste used at their sites and used telephone and written questionnaires to find ``best-in-class`` industrv partners willing to share information about their best waste minimization techniques and technologies through a site visit. Eastman Kodak Co., and Johnson Space Center/National Aeronautics and Space Administration (NASA) agreed to be partners. The site visits yielded strategies for source reduction, recycle/recovery of components, regeneration/reuse of solutions, and treatment of residuals, as well as best management practices. An additional benefit of the work was the opportunity for DOE process experts to network and exchange ideas with their peers at similar sites.

  9. Waste minimization -- Hanford`s strategy for sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Merry, D.S.

    1998-01-30

    The Hanford Site cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single-shell storage tanks, treating waste stored in 28 double-shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored onsite, removing thousands of structures, and dealing with significant solid waste, groundwater, and land restoration issues. The Pollution Prevention/Waste Minimization (P2/WMin) Program supports the Hanford Site mission to safely clean up and manage legacy waste and to develop and deploy science and technology in many ways. Once such way is through implementing and documenting over 231 waste reduction projects during the past five years, resulting in over $93 million in cost savings/avoidances. These savings/avoidances allowed other high priority cleanup work to be performed. Another way is by exceeding the Secretary of Energy`s waste reduction goals over two years ahead of schedule, thus reducing the amount of waste to be stored, treated and disposed. Six key elements are the foundation for these sustained P2/WMin results.

  10. Annual Waste Minimization Summary Report Calendar Year 2007

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2008-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year (CY) 2007. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit (number NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  11. Annual Waste Minimization Summary Report, Calendar Year 2008

    International Nuclear Information System (INIS)

    2009-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2008. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  12. Annual Waste Minimization Summary Report, Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2009. This report was developed in accordance with the requirements of the Nevada Test Site Resource Conservation and Recovery Act Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by NNSA/NSO.

  13. Pollution prevention and waste minimization opportunity assessment in environmental restoration

    International Nuclear Information System (INIS)

    Roybal, J.A.; Willison, C.P.

    1997-01-01

    The Environmental Restoration (ER) Project at Sandia National Laboratories implicitly subscribed to the philosophy of pollution prevention and waste minimization. As a result of a Department of Energy (DOE) offer, Pollution Prevention Opportunity Assessments (PPOA) were conducted at two ER sites and a decontamination and Demolition (D and D) site. The purpose of one of the PPOAs was to identify pollution prevention (P2) opportunities during environmental remediation at the Classified Waste Landfill located at Sandia National Laboratories, New Mexico (SNL/NM). The remediation activities at this site are scheduled to begin in the fall of 1997. The PPOA included presentations by the team members, a tour of the site, and a brainstorming session to list the waste streams, identify P2 opportunities and rank them in order of priority. Twenty-five P2 opportunities were identified during the brainstorming session of which twenty-two opportunities were selected for further investigation. Those twenty-two opportunities are discussed in this paper. A cost benefit analysis was performed for each P2 opportunity based on the estimated waste volume, feasibility, and cost. Pollution Prevention by Design (P2D) was incorporated into the PPOA to introduce waste minimization techniques that can be used during the planning phase of restoration projects

  14. Hanford Site waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This plan, which is required by US Department of Energy (DOE) Order 5400. 1, provides waste minimization and pollution prevention guidance for all Hanford Site contractors. The plan is primary in a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan, Prime contractor implementation plans, and the Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation (DOE-RL, 1997a) describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Items discussed include the pollution prevention policy and regulatory background, organizational structure, the major objectives and goals of Hanford Site's pollution prevention program, and an itemized description of the Hanford Site pollution prevention program. The document also includes US Department of Energy, Richland Operations Office's (RL's) statement of policy on pollution prevention as well as a listing of regulatory drivers that require a pollution prevention program

  15. Best Practice of Construction Waste Management and Minimization

    Directory of Open Access Journals (Sweden)

    Khor Jie Cheng

    2014-07-01

    Full Text Available Material management is an important issue as seen in construction waste management. Best practice of material management is accompanied by various benefits which are acknowledged by several studies. The site layout has particular effects on both materials and their waste through effective waste management practice. Ignoring the benefits of material management could result in a daily reduction in productivity of up to 40% by material wastage. Thus, the benefits of effective material management must be well comprehended for the sake of waste minimization. Another convincing fact about waste is that poor site management accounts for the largest factor of waste generation. Hence the site condition is very crucial in developing effective material management. Factors contributing to the efficiency of material management process are effective logistical management and supply chain management. The logistics system must be performing as schedule so that materials are wisely managed on-site without encountering presence of excessive materials. As materials management is closely related to logistics in construction projects, there will be delay in construction projects when materials are not delivered to site as scheduled. The management must be effective in terms of delivery, off-loading, storage, handling, on-site transportation and on-site utilization of materials.

  16. Development of a waste minimization plan for a Department of Energy remedial action program: Ideas for minimizing waste in remediation scenarios

    International Nuclear Information System (INIS)

    Hubbard, Linda M.; Galen, Glen R.

    1992-01-01

    Waste minimization has become an important consideration in the management of hazardous waste because of regulatory as well as cost considerations. Waste minimization techniques are often process specific or industry specific and generally are not applicable to site remediation activities. This paper will examine ways in which waste can be minimized in a remediation setting such as the U.S. Department of Energy's Formerly Utilized Sites Remedial Action Program, where the bulk of the waste produced results from remediating existing contamination, not from generating new waste. (author)

  17. Waste minimization for commercial radioactive materials users generating low-level radioactive waste

    International Nuclear Information System (INIS)

    Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

    1991-07-01

    The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

  18. Chemical and mechanical decontamination processes to minimize secondary waste decommissioning

    International Nuclear Information System (INIS)

    Enda, M.; Ichikawa, N.; Yaita, Y.; Kanasaki, T.; Sakai, H.

    2008-01-01

    In the decommissioning of commercial nuclear reactors in Japan, prior to the dismantling of the nuclear power plants, there are plans to use chemical techniques to decontaminate reactor pressure vessels (RPVs), internal parts, primary loop recirculation systems (PLRs), reactor water clean up systems (RWCUs), etc., so as to minimize radiation sources in the materials to be disposed of. After dismantling the nuclear power plants, chemical and mechanical decontamination techniques will then be used to reduce the amounts of radioactive metallic waste. Toshiba Corporation has developed pre-dismantling and post-dismantling decontamination systems. In order to minimize the amounts of secondary waste, the T-OZON process was chosen for decontamination prior to the dismantling of nuclear power plants. Dismantling a nuclear power plant results in large amounts of metallic waste requiring decontamination; for example, about 20,000 tons of such waste is expected to result from the dismantling of a 110 MWe Boiling Water Reactor (BWR). Various decontamination methods have been used on metallic wastes in preparation for disposal in consideration of the complexity of the shapes of the parts and the type of material. The materials in such nuclear power plants are primarily stainless steel and carbon steel. For stainless steel parts having simple shapes, such as plates and pipes, major sources of radioactivity can be removed from the surface of the parts by bipolar electrolysis (electrolyte: H 2 SO 4 ). For stainless steel parts having complicated shapes, such as valves and pumps, major sources of radioactivity can be removed from the surfaces by redox chemical decontamination treatments (chemical agent: Ce(IV)). For carbon steel parts having simple shapes, decontamination by blasting with zirconia grit is effective in removing major sources of radioactivity at the surface, whereas for carbon steel parts having complicated shapes, major sources of radioactivity can be removed from

  19. Mixed-waste minimization activities in the nuclear weapons complex

    International Nuclear Information System (INIS)

    Marchetti, J.A.; Suffern, J.S.

    1991-01-01

    Over the past 40 years, the US Department of Energy (DOE) and the nuclear weapons complex have successfully executed their mission of providing the country with a strong nuclear deterrent. Now, however, they must attain another mission at the same time: to eliminate or greatly reduce the environmental, safety, and health problems in the complex. Mixed-waste minimization activities have taken place in 11 of the complex production plants and laboratories: the Pinellas plant, the Mount plant, the Kansas City plant, the Y-12 plant, the Rocky Flats plant, the Savannah River Site (SRS), the Savannah River Site (SRS), the Pantex plant, the Nevada Test Site, Sandia National Laboratories, Los Alamos National Laboratory, and the Lawrence Livermore National Laboratory. The mixed-waste minimization opportunities that have been implemented to date by the production facilities are different from those that have been implemented by the laboratories. Areas of opportunity at the plants involve the following activities: (1) process design or improvement; (2) substitution of materials; (3) waste segregation; (4) recycling; and (5) administrative controls

  20. Using benchmarking to minimize common DOE waste streams: Volume 5. Office paper waste

    Energy Technology Data Exchange (ETDEWEB)

    Levin, V.

    1995-10-01

    Finding innovative ways to reduce waste streams generated at US Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE`s waste minimization efforts. A team composed of members from several DOE facilities used the quality tool known as benchmarking to improve waste minimization efforts. First the team examined office waste generation and handling processes at their sites. Then team members developed telephone and written questionnaires to help identify potential ``best-in-class`` industry partners willing to share information about their best waste minimization techniques and technologies. The team identified two benchmarking partners, NIKE, Inc., in Beaverton, Oregon, and Microsoft, Inc., in Redmond, Washington. Both companies have proactive, employee-driven environmental issues programs. Both companies report strong employee involvement, management commitment, and readily available markets for recyclable materials such as white paper and nonwhite assorted paper. The availability of markets, the initiative and cooperation of employees, and management support are the main enablers for their programs. At both companies, recycling and waste reduction programs often cut across traditional corporate divisions such as procurement, janitorial services, environmental compliance, grounds maintenance, cafeteria operations, surplus sales, and shipping and receiving. These companies exhibited good cooperation between these functions to design and implement recycling and waste reduction programs.

  1. Using benchmarking to minimize common DOE waste streams: Volume 5. Office paper waste

    International Nuclear Information System (INIS)

    Levin, V.

    1995-10-01

    Finding innovative ways to reduce waste streams generated at US Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE's waste minimization efforts. A team composed of members from several DOE facilities used the quality tool known as benchmarking to improve waste minimization efforts. First the team examined office waste generation and handling processes at their sites. Then team members developed telephone and written questionnaires to help identify potential ''best-in-class'' industry partners willing to share information about their best waste minimization techniques and technologies. The team identified two benchmarking partners, NIKE, Inc., in Beaverton, Oregon, and Microsoft, Inc., in Redmond, Washington. Both companies have proactive, employee-driven environmental issues programs. Both companies report strong employee involvement, management commitment, and readily available markets for recyclable materials such as white paper and nonwhite assorted paper. The availability of markets, the initiative and cooperation of employees, and management support are the main enablers for their programs. At both companies, recycling and waste reduction programs often cut across traditional corporate divisions such as procurement, janitorial services, environmental compliance, grounds maintenance, cafeteria operations, surplus sales, and shipping and receiving. These companies exhibited good cooperation between these functions to design and implement recycling and waste reduction programs

  2. Metal decontamination for waste minimization using liquid metal refining technology

    International Nuclear Information System (INIS)

    Joyce, E.L. Jr.; Lally, B.; Ozturk, B.; Fruehan, R.J.

    1993-01-01

    The current Department of Energy Mixed Waste Treatment Project flowsheet indicates that no conventional technology, other than surface decontamination, exists for metal processing. Current Department of Energy guidelines require retrievable storage of all metallic wastes containing transuranic elements above a certain concentration. This project is in support of the National Mixed Low Level Waste Treatment Program. Because of the high cost of disposal, it is important to develop an effective decontamination and volume reduction method for low-level contaminated metals. It is important to be able to decontaminate complex shapes where surfaces are hidden or inaccessible to surface decontamination processes and destruction of organic contamination. These goals can be achieved by adapting commercial metal refining processes to handle radioactive and organic contaminated metal. The radioactive components are concentrated in the slag, which is subsequently vitrified; hazardous organics are destroyed by the intense heat of the bath. The metal, after having been melted and purified, could be recycled for use within the DOE complex. In this project, we evaluated current state-of-the-art technologies for metal refining, with special reference to the removal of radioactive contaminants and the destruction of hazardous organics. This evaluation was based on literature reports, industrial experience, plant visits, thermodynamic calculations, and engineering aspects of the various processes. The key issues addressed included radioactive partitioning between the metal and slag phases, minimization of secondary wastes, operability of the process subject to widely varying feed chemistry, and the ability to seal the candidate process to prevent the release of hazardous species

  3. Chelating water-soluble polymers for waste minimization

    International Nuclear Information System (INIS)

    Smith, B.; Cournoyer, M.; Duran, B.; Ford, D.; Gibson, R.; Lin, M.; Meck, A.; Robinson, P.; Robison, T.

    1996-01-01

    Within the DOE complex and in industry there is a tremendous need for advanced metal ion recovery and waste minimization techniques. This project sought to employ capabilities for ligand-design and separations chemistry in which one can develop and evaluate water- soluble chelating polymers for recovering actinides and toxic metals from various process streams. Focus of this work was (1) to develop and select a set of water-soluble polymers suitable for a selected waste stream and (2) demonstrate this technology in 2 areas: removal of (a) actinides and toxic RCRA metals from waste water and (b) recovery of Cu and other precious metals from industrial process streams including from solid catalysts and aqueous waste streams. The R ampersand D was done in 4 phases for each of the 2 target areas: polymer synthesis for scaleup, equipment assembly, process demonstration at a DOE or industrial site, and advanced ligand/polymer synthesis. The TA- 50 site at Los Alamos was thought to be appropriate due to logistics and to its being representative of similar problems throughout the DOE complex

  4. Waste transmutation with minimal fuel cycle long-term risk

    Energy Technology Data Exchange (ETDEWEB)

    Slessarev, I.; Salvatores, M.; Uematsu, M. [Direction des Reacteurs Nucleaires, Cadarache (France)

    1995-10-01

    Hybrid systems (source-driven subcritical reactors), are investigated at CEA, mainly from a conceptual point of view, in order to assess their potential to transmute radioactive wastes (mainly long-lived fission products, LLFP) and their potential to insure a minimal long-term radiological risk related both to the fuel inventory inside the system and to the full fuel cycle (mass flows, reprocessing transport, waste disposal). The physics of these systems has been explored and work is in progress both in the field of basic data and INC code validation, in the frame of international collaborations and in the field of conceptual design studies. The most interesting feature of subcritical source-driven system is related to the possibility to obtain an {open_quotes}excess{close_quotes} of neutrons per fission, which can be used to reduce the long-term radiological risk. A specific example will be discussed here.

  5. Hazardous waste minimization at Oak Ridge National Laboratory during 1987

    International Nuclear Information System (INIS)

    Kendrick, C.M.

    1988-03-01

    Oak Ridge National Laboratory (ORNL) is a multipurpose research and development facility owned and operated by the Department of Energy (DOE) and managed under subcontract by Martin Marietta Energy Systems, Inc. Its primary role is the support of energy technology through applied research and engineering development and scientific research in basic and physical sciences. ORNL also is a valuable resource in the solution of problems of national importance, such as nuclear and chemical waste management. In addition, useful radioactive and stable isotopes which are unavailable from the private sector are produced at ORNL. A formal hazardous waste minimization program for ORNL was launched in mid-1985 in response to the requirements of Section 3002 of the Resource Conservation and Recovery Act (RCRA). The plan for waste minimization has been modified several times and continues to be dynamic. During 1986, a task plan was developed. The six major tasks include: planning and implementation of a laboratory-wide chemical inventory and the subsequent distribution, treatment, storage, and/or disposal (TSD) of unneeded chemicals; establishment and implementation of a system for distributing surplus chemicals to other (internal and external) organizations; training and communication functions necessary to inform and motivate laboratory personnel; evaluation of current procurement and tracking systems for hazardous materials and recommendation and implementation of improvements; systematic review of applicable current and proposed ORNL procedures and ongoing and proposed activities for waste volume and/or toxicity reduction potential; and establishment of criteria by which to measure progress and reporting of significant achievements. Progress is being made toward completing these tasks and is described in this report. 13 refs., 1 fig., 7 tabs

  6. Gas cylinder disposal pit remediation waste minimization and management

    International Nuclear Information System (INIS)

    Alas, C.A.; Solow, A.; Criswell, C.W.; Spengler, D.; Brannon, R.; Schwender, J.M.; Eckman, C.K.; Rusthoven, T.

    1995-01-01

    A remediation of a gas cylinder disposal pit at Sandia National Laboratories, New Mexico has recently been completed. The cleanup prevented possible spontaneous releases of hazardous gases from corroded cylinders that may have affected nearby active test areas at Sandia's Technical Area III. Special waste management, safety, and quality plans were developed and strictly implemented for this project. The project was conceived from a waste management perspective, and waste minimization and management were built into the planning and implementation phases. The site layout was planned to accommodate light and heavy equipment, storage of large quantities of suspect soil, and special areas to stage and treat gases and reactive chemicals removed from the pit, as well as radiation protection areas. Excavation was a tightly controlled activity using experienced gas cylinder and reactive chemical specialists. Hazardous operations were conducted at night under lights, to allow nearby daytime operations to function unhindered. The quality assurance plan provided specific control of, and documentation for, critical decisions, as well as the record of daily operations. Both hand and heavy equipment excavation techniques were utilized. Hand excavation techniques were utilized. Hand excavation techniques allows sealed glass containers to be exhumed unharmed. In the end, several dozen thermal batteries; 5 pounds (2.3 kg) of lithium metal; 6.6 pounds (3.0 kg) of rubidium metal; several kilograms of unknown chemicals; 140 cubic yards (107 cubic meters) of thorium-contaminated soil; 270 cubic yards (205 cubic meters) of chromium-contaminated soil; and 450 gas cylinders, including 97 intact cylinders containing inert, flammable, toxic, corrosive, or oxidizing gases were removed and effectively managed to minimize waste

  7. Clearance measurements as a tool for waste minimization during decommissioning

    International Nuclear Information System (INIS)

    Konneus, Patrick; Andersson, Veronica; Lindberg, Maria

    2012-01-01

    Clearance, exemption or free release of material from regulatory control are three ways of expressing the same thing, minimizing the amount of waste that needs disposal as radioactive waste and therefor preserving a repository as a national asset. Studsvik Nuclear has utilized the former full body measurement cell as a shielded compartment used for gamma spectroscopy measurements of materials that may be subject to clearance. The cell was moved from its original position by heavy lifting and transport, as it was transported in one piece weighing 53 tonnes. The facility has basically 4 parts, the cell in which the item is place, the rotating table that rotates the item to get the best possible measurement, the ISOCS that measure the gamma rays and the operator room from which the facility runs. The detector is a BEGe with a relative efficiency of 50 % and is provided by Canberra. Apex is used as software for acquisition, calibration and data storage. The cell can take Bergloefs boxes up to a volume of 1.2m 3 and a weight of 3 tonnes can be rotated on the table. Other standard geometries are drums of 100 or 200 liters. The shielding improves the background radiation to a level where a measurement time of only 1200 s for a standard object (100 L/200 L drum, Bergloefs box) is needed. This means a high daily capacity of measurements. During 2011 measurements have been done on several different materials and together with sampling for alpha emitting nuclides the material has been released from regulatory control and either recycled or disposed of in a standard landfill or a land fill for hazardous waste. The materials released are copper from cable shredding that was measured, samples and recycled about 14 tonnes, titanium tubes about 35 tonnes also recycled and fiberglass/epoxy that has been released for waste treatment in a non-radioactive treatment facility. Measurements have also been done of waste with complex geometries. (authors)

  8. Swords into plowshares -- Tritium waste minimization (training development project)

    International Nuclear Information System (INIS)

    Hehmeyer, J.; Sienkiewicz, C.; Kent, L.; Gill, J.; Schmitz, W.; Mills, T.; Wurstner, R.; Adams, F.; Seabaugh, P.

    1995-01-01

    A concentrated emphasis of Mound's historical mission has been working with tritium. As the phase out of defense work begins and the increase on environmental technology strengthens, so too must a shift occur in applying one's focus. Mound's longstanding efforts in Tritium Training have proven fruitful to them and the Complex. It is this emphasis for which a new generation of worker training is being developed, one which reflects a new mission; Tritium Waste Minimization. The efforts of previous training, particularly under Accreditation, have given a solid base on which to launch the Waste Minimization program. Typical operations consider the impact on the varying levels of containment and the tools and agents used to achieve those levels. D and D and system modifications are bringing new light to such things as floor tile, oils, mole sieves, and rust. Of financial interest is the amount of savings which have been obtained through review and modification, rather than developing a new program. The authors are learning not to reinvent the wheel. The presentation will compare and contrast the methodologies used in creating and implementing this training program. Emphasis will be placed on lessons learned, costs saved, and program enhancement

  9. Waste minimization in analytical chemistry through innovative sample preparation techniques

    International Nuclear Information System (INIS)

    Smith, L. L.

    1998-01-01

    Because toxic solvents and other hazardous materials are commonly used in analytical methods, characterization procedures result in significant and costly amount of waste. We are developing alternative analytical methods in the radiological and organic areas to reduce the volume or form of the hazardous waste produced during sample analysis. For the radiological area, we have examined high-pressure, closed-vessel microwave digestion as a way to minimize waste from sample preparation operations. Heated solutions of strong mineral acids can be avoided for sample digestion by using the microwave approach. Because reactivity increases with pressure, we examined the use of less hazardous solvents to leach selected contaminants from soil for subsequent analysis. We demonstrated the feasibility of this approach by extracting plutonium from a NET reference material using citric and tartaric acids with microwave digestion. Analytical results were comparable to traditional digestion methods, while hazardous waste was reduced by a factor often. We also evaluated the suitability of other natural acids, determined the extraction performance on a wider variety of soil types, and examined the extraction efficiency of other contaminants. For the organic area, we examined ways to minimize the wastes associated with the determination of polychlorinated biphenyls (PCBs) in environmental samples. Conventional methods for analyzing semivolatile organic compounds are labor intensive and require copious amounts of hazardous solvents. For soil and sediment samples, we have a method to analyze PCBs that is based on microscale extraction using benign solvents (e.g., water or hexane). The extraction is performed at elevated temperatures in stainless steel cells containing the sample and solvent. Gas chromatography-mass spectrometry (GC/MS) was used to quantitate the analytes in the isolated extract. More recently, we developed a method utilizing solid-phase microextraction (SPME) for natural

  10. Waste minimization fundamental principles used in radioactive waste management plan for decommissioning of a CANDU - 600 nuclear power plant

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Georgescu, Roxana Cristiana; Sociu, Florin

    2009-01-01

    The objectives of waste minimization are to limit the generation and spread of radioactive contamination and to reduce the amount of wastes for storage and disposal, thereby limiting any consequent environmental impact, as well as the total costs associated with contaminated material management. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from Decontamination and Decommissioning (D and D) activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during Decontamination and Decommissioning. The main elements of a waste minimization strategy can be grouped into four areas: source reduction, prevention of contamination spread, recycle and reuse, and waste management optimization. For sustaining this objective, the following principles and procedures of wastes management are taken into account: safety and environment protection principles; principles regarding the facility operation; quality assurance procedures; procedures for material classification and releasing. (authors)

  11. Proceedings of pollution prevention and waste minimization tools workshop

    International Nuclear Information System (INIS)

    1995-01-01

    Pollution Prevention (P2) has evolved into one of DOE's sprime strategies to meet environmental, fiscal, and worker safety obligations. P2 program planning, opportunity identification, and implementation tools were developed under the direction of the Waste Minimization Division (EM-334). Forty experts from EM, DP, ER and DOE subcontractors attended this 2-day workshop to formulate the incentives to drive utilization of these tools. Plenary and small working group sessions were held both days. Working Group 1 identified incentives to overcoming barriers in the area of P2 program planning and resource allocation. Working Group 2 identified mechanisms to drive the completion of P2 assessments and generation of opportunities. Working Group 3 compiled and documented a broad range of potential P2 incentives that address fundamental barriers to implementation of cost effective opportunities

  12. Landfill life expectancy with waste reduction/minimization

    International Nuclear Information System (INIS)

    Klan, M.S.

    1990-01-01

    Although some minimally acceptable practices are presently undertaken at most landfills to protect human health and safety and the environment, a key question remains. How much effort and resources should be expended to slow the fill-rate of a landfill? The answer depends on the performance and costs of the technical options available, the difficulty and cost of acquiring additional landfill space, and the consequences for remaining landfill lifetime of current and future actions. Toward this end, the paper (1) presents a method for projecting the remaining life of a landfill, including the alternative lifetimes associated with life extension measures; (2) presents a case study of the low-level waste landfill at Los Alamos National Lab.; and (3) illustrates a procedure for determining which measures become cost-effective to adopt as a landfill's space declines

  13. Actinide removal from wastewater applying waste minimization techniques

    International Nuclear Information System (INIS)

    Covey, J.R.; Midkiff, W.S.; Cadena, F.

    1992-01-01

    A major concern at LANL is the large volume of low level radioactive sludge that is generated by the current treatment technology. The plant meets current discharge limits but annually produces 200 55-gallon drums of sludge (approximately 60 tons) during the process of removing only few grants of radioactive isotopes. Most of the sludge results from the coagulants, iron and lime, added at the plant at a concentration of 10,000 parts-per-million (ppm). If the principal actinides in the influent could be separated and reduced to pure metallic form, the annual volume of plutonium would be about the size of a marble and the americium would be about the size of a BB. Waste minimization will be a key design criteria for the new facility. Records of total suspended solids (TSS) in the influent average about 1000 Kg per year (approximately 1 ton). Therefore, the theoretical sludge volume reduction is near 98%. Research is underway to develop and evaluate technologies that achieve the desired removal efficiency with a minimum of produced waste volume

  14. The IFR pyroprocessing for high-level waste minimization

    International Nuclear Information System (INIS)

    Laidler, J.J.

    1993-01-01

    The process developed for the recycle of integral fast reactor (IFR) spent fuel utilizes a combination of pyrometallurgical and electrochemical methods and has been termed pyroprocessing. The process has been operated at full scale with simulated spent fuel using nonradioactive fission product elements. A comprehensive demonstration of the pyroprocessing of irradiated IFR fuel will begin later this year. Pyroprocessing involves the anodic dissolution of all the constituent elements of the IFR spent fuel and controlled electrotransport (electrorefining) to separate the actinide elements from the fission products present in the spent fuel. The process be applied to the processing of spent light water reactor (LWR) fuel as well, requiring only the addition of a reduction step to convert the LWR fuel as well, requiring only the addition of a reduction step to convert the LWR oxide fuel to metallic form and a separation step to separate uranium from the transuranic (TRU) elements. The TRU elements are then recovered by electroefining in the same manner as the actinides from the IFR high-level wastes arising from pyroprocessing are virtually free of actinides, and the volume of the wastes is minimized by the intrinsic characteristics of the processing of the processing method

  15. Process innovations to minimize waste volumes at Savannah River

    International Nuclear Information System (INIS)

    Doherty, J.P.

    1986-01-01

    In 1983 approximately 1.6 x 10 3 m 3 (427,000 gallons) of radioactive salt solution were decontaminated in a full-scale demonstration. The cesium decontamination factor (DF) was in excess of 4 x 10 4 vs. a goal of 1 x 10 4 . Data from this test were combined with pilot data and used to design the permanent facilities currently under construction. Startup of the Salt Decontamination Process is scheduled for 1987 and will decontaminate 2 x 10 4 m 3 (5.2 million gallons) of radioactive salt solution and generate 2 x 10 3 m 3 (520,000 gallons) of concentrated and washed precipitate per year. The Defense Waste Processing Facility (DWPF) will begin processing this concentrate in the Precipitate Hydrolysis Process starting in 1989. Laboratory data using simulated salt solution and nonradioactive cesium are being used to design this process. A 1/5-scale pilot plant is under construction and will be used to gain large-scale operating experience using nonradioactive simulants. This pilot plant is scheduled to startup in early 1987. The incentives to reduce the volume of waste that must be treated are self-evident. At Savannah River process development innovations to minimize the DWPF feed volumes have directly improved the economics of the process. The integrity of the final borosilicate glass water form has not been compromised by these developments. Many of the unit operations are familiar to chemical engineers and were put to use in a unique environment. As a result, tax dollars have been saved, and the objective of safely disposing of the nation's high-level defense waste has moved forward

  16. Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Peters, R.W.; Wentz, C.A.; Thuot, J.R.

    1991-01-01

    In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot demonstration of the how the ANL Plan audited the hazardous waste generated within a selected divisions of ANL. It includes quantitative data on the generation and disposal of hazardous waste at ANL and describes potential ways to minimize hazardous wastes. 2 refs., 5 figs., 8 tabs

  17. INTELLIGENT DECISION SUPPORT FOR WASTE MINIMIZATION IN ELECTROPLATING PLANTS. (R824732)

    Science.gov (United States)

    AbstractWastewater, spent solvent, spent process solutions, and sludge are the major waste streams generated in large volumes daily in electroplating plants. These waste streams can be significantly minimized through process modification and operational improvement. I...

  18. Environmental Restoration Progam Waste Minimization and Pollution Prevention Awareness Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Grumski, J. T.; Swindle, D. W.; Bates, L. D.; DeLozier, M. F.P.; Frye, C. E.; Mitchell, M. E.

    1991-09-30

    In response to DOE Order 5400.1 this plan outlines the requirements for a Waste Minimization and Pollution Prevention Awareness Program for the Environmental Restoration (ER) Program at Martin Marietta Energy System, Inc. Statements of the national, Department of Energy, Energy Systems, and Energy Systems ER Program policies on waste minimization are included and reflect the attitudes of these organizations and their commitment to the waste minimization effort. Organizational responsibilities for the waste minimization effort are clearly defined and discussed, and the program objectives and goals are set forth. Waste assessment is addressed as being a key element in developing the waste generation baseline. There are discussions on the scope of ER-specific waste minimization techniques and approaches to employee awareness and training. There is also a discussion on the process for continual evaluation of the Waste Minimization Program. Appendixes present an implementation schedule for the Waste Minimization and Pollution Prevention Program, the program budget, an organization chart, and the ER waste minimization policy.

  19. Environmental Restoration Progam Waste Minimization and Pollution Prevention Awareness Program Plan

    International Nuclear Information System (INIS)

    1991-01-01

    In response to DOE Order 5400.1 this plan outlines the requirements for a Waste Minimization and Pollution Prevention Awareness Program for the Environmental Restoration (ER) Program at Martin Marietta Energy System, Inc. Statements of the national, Department of Energy, Energy Systems, and Energy Systems ER Program policies on waste minimization are included and reflect the attitudes of these organizations and their commitment to the waste minimization effort. Organizational responsibilities for the waste minimization effort are clearly defined and discussed, and the program objectives and goals are set forth. Waste assessment is addressed as being a key element in developing the waste generation baseline. There are discussions on the scope of ER-specific waste minimization techniques and approaches to employee awareness and training. There is also a discussion on the process for continual evaluation of the Waste Minimization Program. Appendixes present an implementation schedule for the Waste Minimization and Pollution Prevention Program, the program budget, an organization chart, and the ER waste minimization policy

  20. Good Practice Guide Waste Minimization/Pollution Prevention

    Energy Technology Data Exchange (ETDEWEB)

    J Dorsey

    1999-10-14

    This Good Practice Guide provides tools, information, and examples for promoting the implementation of pollution prevention during the design phases of U.S. Department of Energy (DOE) projects. It is one of several Guides for implementing DOE Order 430.1, Life-cycle Asset Management. DOE Order 430.1 provides requirements for DOE, in partnership with its contractors, to plan, acquire, operate, maintain, and dispose of physical assets. The goals of designing for pollution prevention are to minimize raw material consumption, energy consumption, waste generation, health and safety impacts, and ecological degradation over the entire life of the facility (EPA 1993a). Users of this Guide will learn to translate national policy and regulatory requirements for pollution prevention into action at the project level. The Guide was written to be applicable to all DOE projects, regardless of project size or design phase. Users are expected to interpret the Guide for their individual project's circumstances, applying a graded approach so that the effort is consistent with the anticipated waste generation and resource consumption of the physical asset. This Guide employs a combination of pollution prevention opportunity assessment (PPOA) methods and design for environment (DfE) philosophies. The PPOA process was primarily developed for existing products, processes, and facilities. The PPOA process has been modified in this Guide to address the circumstances of the DOE design process as delineated in DOE Order 430.1 and its associated Good Practice Guides. This modified form of the PPOA is termed the Pollution Prevention Design Assessment (P2DA). Information on current nationwide methods and successes in designing for the environment also have been reviewed and are integrated into this guidance.

  1. Good Practice Guide Waste Minimization/Pollution Prevention; TOPICAL

    International Nuclear Information System (INIS)

    J Dorsey

    1999-01-01

    This Good Practice Guide provides tools, information, and examples for promoting the implementation of pollution prevention during the design phases of U.S. Department of Energy (DOE) projects. It is one of several Guides for implementing DOE Order 430.1, Life-cycle Asset Management. DOE Order 430.1 provides requirements for DOE, in partnership with its contractors, to plan, acquire, operate, maintain, and dispose of physical assets. The goals of designing for pollution prevention are to minimize raw material consumption, energy consumption, waste generation, health and safety impacts, and ecological degradation over the entire life of the facility (EPA 1993a). Users of this Guide will learn to translate national policy and regulatory requirements for pollution prevention into action at the project level. The Guide was written to be applicable to all DOE projects, regardless of project size or design phase. Users are expected to interpret the Guide for their individual project's circumstances, applying a graded approach so that the effort is consistent with the anticipated waste generation and resource consumption of the physical asset. This Guide employs a combination of pollution prevention opportunity assessment (PPOA) methods and design for environment (DfE) philosophies. The PPOA process was primarily developed for existing products, processes, and facilities. The PPOA process has been modified in this Guide to address the circumstances of the DOE design process as delineated in DOE Order 430.1 and its associated Good Practice Guides. This modified form of the PPOA is termed the Pollution Prevention Design Assessment (P2DA). Information on current nationwide methods and successes in designing for the environment also have been reviewed and are integrated into this guidance

  2. Methods for the minimization of radioactive waste from decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this report is to provide Member States and their decision makers (ranging from regulators, strategists, planners and designers, to operators) with relevant information on opportunities for minimizing radioactive wastes arising from the D and D of nuclear facilities. This will allow waste minimization options to be properly planned and assessed as part of national, site and plant waste management policies. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from D and D activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during D and D

  3. LEAN HEALTHCARE SUPPLY CHAIN MANAGEMENT: MINIMIZING WASTE AND COSTS

    Directory of Open Access Journals (Sweden)

    Catia M L Machado

    2014-12-01

    Full Text Available The purpose of this research is to investigate the management models applied in the supply chain providing services in healthcare organizations, considering the lenses of lean. The aim of this is to develop a model of supply chain management focusing on the identification and minimization of waste, assisting in decision making and contributing to the quality of services and as a consequence the reduction of the costs involved in healthcare supply chain. The philosophies of continuous improvement and lean techniques have a role to play in helping healthcare to provide quality service and support to reduce costs in the current budget constraints. In the supply chain of hospitals the financial costs can be around 40% of its budget (MASOUMI et al. 2012; SOUZA et al., 2013. This article sheds light on the improvement in decision making and the effect of reducing costs in the healthcare supply chain. In this sense, the research intend to expand knowledge related to supply chain management in the area of ​​provision of healthcare services through the use of the philosophy of continuous improvement and lean principles, helping healthcare to provide quality service within their current budget constraints.

  4. 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

  5. Headquarters Air Force Logistics Command guidance manual for hazardous waste minimization (PACER REDUCE): Hazardous Waste Remedial Actions Program

    International Nuclear Information System (INIS)

    Jones, L.W.; Weeter, D.; Roth, J.A.; Debelak, K.A.; Bowers, A.R.

    1988-09-01

    This manual provides guidance for the Air Force Logistics Command (AFLC) Waste Minimization Program, called PACER REDUCE, and applies to all AFLC installations and personel who are responsible for implementing and monitoring activities relating to PACER REDUCE. This guidance for waste minimization provides management and technical approaches for assessing potential waste reduction techniques and for making informed decisions concerning industrial process and waste stream management. Such actions will assist in achieving regulatory compliance with the Resource Conservation and Recovery Act of 1976 as updated by the Hazardous and Solid Waste Amendments of 1984. 37 refs., 14 figs., 22 tabs

  6. Proceedings of the Department of Energy Defense Programs hazardous and mixed waste minimization workshop: Hazardous Waste Remedial Actions Program

    International Nuclear Information System (INIS)

    1988-09-01

    The first workshop on hazardous and mixed waste minimization was held in Las Vegas, Nevada, on July 26--28, 1988. The objective of this workshop was to establish an interchange between DOE headquarters (DOE-HQ) DP, Operations Offices, and contractors of waste minimization strategies and successes. The first day of the workshop began with presentations stressing the importance of establishing a waste minimization program at each site as required by RCRA, the land ban restrictions, and the decrease in potential liabilities associated with waste disposal. Discussions were also centered on pending legislation which would create an Office of Waste Reduction in the Environmental Protection Agency (EPA). The Waste Minimization and Avoidance Study was initiated by DOE as an addition to the long-term productivity study to address the issues of evolving requirements facing RCRA waste management activities at the DP sites, to determine how major operations will be affected by these requirements, and to determine the available strategies and options for waste minimization and avoidance. Waste minimization was defined in this study as source reduction and recycling

  7. WASTE MINIMIZATION ASSESSMENT FOR A MANUFACTURER OF CUTTING AND WELDING EQUIPMENT

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot program to assist small and medium-size manufacturers who want to minimize their generation of waste but who lack the expertise to do so in an effort to assist these manufacturers Waste Minimization Assessment Cent...

  8. ENVIRONMENTAL RESEARCH BRIEF: WASTE MINIMIZATION FOR A MANUFACTURER OF COMPRESSED AIR EQUIPMENT COMPONENTS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium-size manufacturers who want to minimize their generation of hazardous waste but lack the expertise to do so. Waste Minimization Assessment Centers (WMACs) were established at sel...

  9. WASTE MINIMIZATION ASSESSMENT FOR A MANUFACTURER OF CUSTOM MOLDED PLASTIC PRODUCTS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium-size manufacturers who want to minimize their generation of waste but who lack the expertise to do so. Waste Minimization Assessment Centers (WMACs) were established at selected ...

  10. ENVIRONMENTAL RESEARCH BRIEF: WASTE MINIMIZATION ASSESSMENT FOR A MANUFACTURER OF PRINTED PLASTIC BAGS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium-size manufacturers who want to minimize their generation of hazardous waste but who lack the expertise to do so. Waste Minimization Assessment Centers (WMACs) were established ...

  11. WASTE MINIMIZATION ASSESSMENT FOR A MANUFACTURER OF SILICON-CONTROLLED RECTIFIERS AND SCHOTTKY RECTIFIERS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium-size manufacturers who want to minimize their generation of waste but who lack the expertise to do so. In an effort to assist these manufacturers Waste Minimization Assessment Ce...

  12. ENVIRONMENTAL RESEARCH BRIEF: WASTE MINIMIZATION ASSESSMENT FOR A MANUFACTURER OF REBUILT RAILWAY CARS AND COMPONENTS

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium- size manufacturers who want to minimize their generation of hazardous waste but lack the expertise to do so. Waste Minimization Assessment Centers (WMACs) were established at se...

  13. Integration of environmentally compatible soldering technologies for waste minimization

    International Nuclear Information System (INIS)

    Hosking, F.M.

    1992-01-01

    There has been a concentrated effort throughout the international microelectronics industry to phase out chlorofluorocarbon (CFC) materials and alleviate the serious problem of ozone depletion created by the release of CFCS. The development of more environmentally compatible manufacturing technologies is the cornerstone of this effort. Alternative materials and processes for cleaning and soldering have received special attention. Electronic. soldering typically utilizes rosin-based fluxes to promote solder wettability. Flux residues must be removed from the soldered parts when high product reliability is essential. Halogenated or CFC solvents have been the principle chemicals used to clean the residues. With the accelerated push to eliminate CFCs in the US by 1995, CFC-free solvents, aqueous-based cleaning, water soluble or ''no clean'' fluxes, and fluxless soldering technologies are being developed and quickly integrated into manufacturing practice. Sandia's Center for Solder Science and Technology has been ch g a variety of fluxless and alternative soldering technologies for DOE's waste minimization program. The work has focused on controlled atmosphere, laser, and ultrasonic fluxless soldering, protective metallic and organic coatings, and fluxes which have water soluble or low solids-based chemistries. With the increasing concern that Pb will also be banned from electronic soldering, Sandia has been characterizing the wetting, aging, and mechanical properties of Pb-fire solder alloys. The progress of these integrated studies will be discussed. Their impact on environmentally compatible manufacturing will be emphasized. Since there is no universal solution to the various environmental, safety, and health issues which currently face industry, the proposed technologies offer several complementary materials and processing options from which one can choose

  14. ALPHA WASTE MINIMIZATION IN TERMS OF VOLUME AND RADIOACTIVITY AT COGEMA'S MELOX AND LA HAGUE PLANTS

    International Nuclear Information System (INIS)

    ARSLAN, M.; DUMONT, J.C.; LONDRES, V.; PONCELET, F.J.

    2003-01-01

    This paper describes the management of alpha waste that cannot be stored in surface repositories under current French regulations. The aim of the paper is to provide an overview of COGEMA's Integrated Waste Management Strategy. The topics discussed include primary waste minimization, from facility design to operating feedback; primary waste management by the plant operator, including waste characterization; waste treatment options that led to building waste treatment industrial facilities for plutonium decontamination, compaction and cement solidification; and optimization of industrial tools, which is strongly influenced by safety and financial considerations

  15. Information processing to determine waste minimization/pollution prevention strategies in the petroleum industry

    Energy Technology Data Exchange (ETDEWEB)

    Falcon, Mariali F. de [CORPOVEN, S.A. (Venezuela)

    1993-12-31

    With the passage of the 1984 Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act in the United States, industries, and particularly the petroleum industry, have become more interested in their waste management practices. This works aims to present a methodology to organize the collected data concerning waste minimization and, or, pollution prevention in the petroleum industry into a bibliographic database

  16. Trends for minimization of radioactive waste arising from spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Polyakov, A.S.; Koltunov, V.S.; Marchenko, V.I.; Ilozhev, A.P.; Mukhin, I.V.

    2000-01-01

    Research and development of technologies for radioactive waste (RAW) minimization arising from spent nuclear fuel reprocessing are discussed. Novel reductants of Pu and Np ions, reagents of purification recycled extractant, possibility of the electrochemical methods are studied. The partitioning of high activity level waste are considered. Examples of microbiological methods decomposition of radioactive waste presented. (authors)

  17. Information processing to determine waste minimization/pollution prevention strategies in the petroleum industry

    Energy Technology Data Exchange (ETDEWEB)

    Falcon, Mariali F. de [CORPOVEN, S.A. (Venezuela)

    1994-12-31

    With the passage of the 1984 Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act in the United States, industries, and particularly the petroleum industry, have become more interested in their waste management practices. This works aims to present a methodology to organize the collected data concerning waste minimization and, or, pollution prevention in the petroleum industry into a bibliographic database

  18. Waste Minimization Improvements Achieved Through Six Sigma Analysis Result In Significant Cost Savings

    International Nuclear Information System (INIS)

    Mousseau, Jeffrey D.; Jansen, John R.; Janke, David H.; Plowman, Catherine M.

    2003-01-01

    Improved waste minimization practices at the Department of Energy's (DOE) Idaho National Engineering and Environmental Laboratory (INEEL) are leading to a 15% reduction in the generation of hazardous and radioactive waste. Bechtel, BWXT Idaho, LLC (BBWI), the prime management and operations contractor at the INEEL, applied the Six Sigma improvement process to the INEEL Waste Minimization Program to review existing processes and define opportunities for improvement. Our Six Sigma analysis team: composed of an executive champion, process owner, a black belt and yellow belt, and technical and business team members used this statistical based process approach to analyze work processes and produced ten recommendations for improvement. Recommendations ranged from waste generator financial accountability for newly generated waste to enhanced employee recognition programs for waste minimization efforts. These improvements have now been implemented to reduce waste generation rates and are producing positive results

  19. Westinghouse Hanford Company waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    Craig, P.A.; Nichols, D.H.; Lindsey, D.W.

    1991-08-01

    The purpose of this plan is to establish the Westinghouse Hanford Company's Waste Minimization Program. The plan specifies activities and methods that will be employed to reduce the quantity and toxicity of waste generated at Westinghouse Hanford Company (Westinghouse Hanford). It is designed to satisfy the US Department of Energy (DOE) and other legal requirements that are discussed in Subsection C of the section. The Pollution Prevention Awareness Program is included with the Waste Minimization Program as permitted by DOE Order 5400.1 (DOE 1988a). This plan is based on the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan, which directs DOE Field Office, Richland contractors to develop and maintain a waste minimization program. This waste minimization program is an organized, comprehensive, and continual effort to systematically reduce waste generation. The Westinghouse Hanford Waste Minimization Program is designed to prevent or minimize pollutant releases to all environmental media from all aspects of Westinghouse Hanford operations and offers increased protection of public health and the environment. 14 refs., 2 figs., 1 tab

  20. Zone Freezing Study for Pyrochemical Process Waste Minimization

    Energy Technology Data Exchange (ETDEWEB)

    Ammon Williams

    2012-05-01

    Pyroprocessing technology is a non-aqueous separation process for treatment of used nuclear fuel. At the heart of pyroprocessing lies the electrorefiner, which electrochemically dissolves uranium from the used fuel at the anode and deposits it onto a cathode. During this operation, sodium, transuranics, and fission product chlorides accumulate in the electrolyte salt (LiCl-KCl). These contaminates change the characteristics of the salt overtime and as a result, large volumes of contaminated salt are being removed, reprocessed and stored as radioactive waste. To reduce the storage volumes and improve recycling process for cost minimization, a salt purification method called zone freezing has been proposed at Korea Atomic Energy Research Institute (KAERI). Zone freezing is melt crystallization process similar to the vertical Bridgeman method. In this process, the eutectic salt is slowly cooled axially from top to bottom. As solidification occurs, the fission products are rejected from the solid interface and forced into the liquid phase. The resulting product is a grown crystal with the bulk of the fission products near the bottom of the salt ingot, where they can be easily be sectioned and removed. Despite successful feasibility report from KAERI on this process, there were many unexplored parameters to help understanding and improving its operational routines. Thus, this becomes the main motivation of this proposed study. The majority of this work has been focused on the CsCl-LiCl-KCl ternary salt. CeCl3-LiCl-KCl was also investigated to check whether or not this process is feasible for the trivalent species—surrogate for rare-earths and transuranics. For the main part of the work, several parameters were varied, they are: (1) the retort advancement rate—1.8, 3.2, and 5.0 mm/hr, (2) the crucible lid configurations—lid versus no-lid, (3) the amount or size of mixture—50 and 400 g, (4) the composition of CsCl in the salt—1, 3, and 5 wt%, and (5) the

  1. Environmental Restoration Program waste minimization and pollution prevention self-assessment

    International Nuclear Information System (INIS)

    1994-10-01

    The Environmental Restoration (ER) Program within Martin Marietta Energy Systems, Inc. is currently developing a more active waste minimization and pollution prevention program. To determine areas of programmatic improvements within the ER Waste Minimization and Pollution Prevention Awareness Program, the ER Program required an evaluation of the program across the Oak Ridge K-25 Site, the Oak Ridge National Laboratory, the Oak Ridge Y-12 Plant, the Paducah Environmental Restoration and Waste Minimization Site, and the Portsmouth Environmental Restoration and Waste Minimization Site. This document presents the status of the overall program as of fourth quarter FY 1994, presents pollution prevention cost avoidance data associated with FY 1994 activities, and identifies areas for improvement. Results of this assessment indicate that the ER Waste Minimization and Pollution Prevention Awareness Program is firmly established and is developing rapidly. Several procedural goals were met in FY 1994 and many of the sites implemented ER waste minimization options. Additional growth is needed, however, for the ER Waste Minimization and Pollution Prevention Awareness Program

  2. LLNL NESHAPs, 1993 annual report

    International Nuclear Information System (INIS)

    Harrach, R.J.; Surano, K.A.; Biermann, A.H.; Gouveia, F.J.; Fields, B.C.; Tate, P.J.

    1994-06-01

    The standard defined in NESHAPSs CFR Part 61.92 limits the emission of radionuclides to the ambient air from DOE facilities to those that would cause any member of the public to receive in any year an effective dose equivalent of 10 mrem. In August 1993 DOE and EPA signed a Federal Facility Compliance Agreement which established a schedule of work for LLNL to perform to demonstrate compliance with NESHAPs, 40 CFR part 61, Subpart H. The progress in LLNL's NESHAPs program - evaluations of all emission points for the Livermore site and Site 300, of collective EDEs for populations within 80 km of each site, status in reguard to continuous monitoring requirements and periodic confirmatory measurements, improvements in the sampling and monitoring systems and progress on a NESHAPs quality assurance program - is described in this annual report. In April 1994 the EPA notified DOE and LLNL that all requirements of the FFCA had been met, and that LLNL was in compliance with the NESHAPs regulations

  3. Minimalism

    CERN Document Server

    Obendorf, Hartmut

    2009-01-01

    The notion of Minimalism is proposed as a theoretical tool supporting a more differentiated understanding of reduction and thus forms a standpoint that allows definition of aspects of simplicity. This book traces the development of minimalism, defines the four types of minimalism in interaction design, and looks at how to apply it.

  4. Waste minimization/pollution prevention at R ampersand D facilities: Implementing the SNL/NM Process Waste Assessment Program

    International Nuclear Information System (INIS)

    Kjeldgaard, E.A.; Stermer, D.L.; Saloio, J.H. Jr.; Lorton, G.A.

    1993-01-01

    The Sandia National Laboratories, New Mexico (SNL/NM) Process Waste Assessment (PWA) program began formally on November 2, 1992. This program represents the first laboratory-wide attempt to explicitly identify and characterize SNL/NM's waste generating processes for waste minimization purposes. This paper describes the major elements of the SNL/NM PWA program, the underlying philosophy for designing a PWA program at a highly diverse laboratory setting such as SNL/NM, and the experiences and insights gained from five months of implementing this living program. Specifically, the SNL/NM PWA program consists of four major, interrelated phases: (1) Process Definition, (2) Process Characterization, (3) Waste Minimization Opportunity Assessment, and (4) Project Evaluation, Selection, Implementation, and Tracking. This phased approach was developed to Provide a flexible, yet appropriate, level of detail to the multitude of different ''processes'' at SNL/NM. Using a staff infrastructure of approximately 60 Waste Minimization Network Representatives (MinNet Reps) and consulting support, the SNL/NM PWA program has become the linchpin of even more progressive and proactive environmental, safety, and health (ES ampersand H) initiatives such as: (1) cradle-to-grove material/waste tracking, (2) centralized ES ampersand H reporting, and (3) detailed baselining and tracking for measuring multi-media waste reduction goals. Specific examples from the SNL/NM PWA program are provided, including the results from Process Definition, Process Characterization, and Waste Minimization Opportunity Assessments performed for a typical SNL/NM process

  5. 40 CFR 63.1213 - How can the compliance date be extended to install pollution prevention or waste minimization...

    Science.gov (United States)

    2010-07-01

    ... to install pollution prevention or waste minimization controls? 63.1213 Section 63.1213 Protection of... pollution prevention or waste minimization controls? (a) Applicability. You may request from the... must contain the following information: (i) A description of pollution prevention or waste minimization...

  6. Waste minimization: A team approach at McGuire nuclear

    International Nuclear Information System (INIS)

    Poteat, E.L.

    1995-01-01

    The production of radioactive waste and its subsequent disposal is a costly proposition. Burial of low-level waste (LLW), if available at all, is expensive and getting more so. The availability of disposal options is often subject to the whims and vagaries of political forces that cannot be predicted, let alone controlled in any way by the members of the nuclear community. On-site storage is a limited and, quite often, an extremely difficult process to put into place. After LLW has been generated, various volume reduction techniques are available, but these can vary widely in cost and effectiveness. If and when new disposal sites are available, the waste acceptance criteria may be such that some or all of the volume reduction processes will not produce an acceptable final waste form. Consequently, the best thing to do is probably deceptively simple: Do not generate the waste in the first place. This is the philosophy that McGuire nuclear station operates under, and this paper discusses the team approach that has been developed to support this idea

  7. Community participation in waste minimization : the case of Emfuleni Local Municipality / Nompazamo Alma Ludidi

    OpenAIRE

    Ludidi, Nompazamo Alma

    2009-01-01

    The purpose of this research is to understand factors contributing to successes and challenges in community participation especially in waste minimization initiatives; in order to inform policies and contribute to improve the design of the initiative. The objectives of the research are: firstly, to understand the current state of public participation in waste minimization at Emfuleni Local Municipality. Secondly, it is to determine the extent of willingness of the community to participate in ...

  8. Westinghouse integrated cementation facility. Smart process automation minimizing secondary waste

    International Nuclear Information System (INIS)

    Fehrmann, H.; Jacobs, T.; Aign, J.

    2015-01-01

    The Westinghouse Cementation Facility described in this paper is an example for a typical standardized turnkey project in the area of waste management. The facility is able to handle NPP waste such as evaporator concentrates, spent resins and filter cartridges. The facility scope covers all equipment required for a fully integrated system including all required auxiliary equipment for hydraulic, pneumatic and electric control system. The control system is based on actual PLC technology and the process is highly automated. The equipment is designed to be remotely operated, under radiation exposure conditions. 4 cementation facilities have been built for new CPR-1000 nuclear power stations in China

  9. Barriers to development and deployment of innovative waste minimization technologies

    International Nuclear Information System (INIS)

    Flores, E.A.; Donaghue, J.F.

    1994-08-01

    Increasing regulation and scrutiny is driving waste generators towards reducing the use of scarce natural resources and reducing or eliminating was streams. There is increasing emphasis on developing and deploying technologies that meet industry needs for recovering valuable materials in a cost-effective manner. At the Department of Energy's (DOE) Hanford Site, Battelle operates Pacific Northwest Laboratory (PNL). PNL's mission is to develop technologies to clean up the environment, and to assist industry in being competitive on a global scale. One such technology developed by PNL is the Waste Acid Detoxification and Reclamation (WADR) process. This technology recovers acids from metal-bearing spent solutions, separating out the metals (which are a valuable byproduct of the acid recycling operation) from the acids. WADR uses selective precipitation and distillation together in an innovative waste recycling technology. Selective precipitation removes the heavy metals, and vacuum distillation recovers clean acid. However, WADR and other innovative waste reduction technologies face numerous barriers to successful development and deployment in the field

  10. Six Strategies for Chemical Waste Minimization in Laboratories.

    Science.gov (United States)

    Matteson, Gary C.; Hadley, Cheri R.

    1991-01-01

    Guidelines are offered to research administrators for reducing the volume of hazardous laboratory waste. Suggestions include a chemical location inventory, a chemical reuse facility, progressive contracts with chemical suppliers, internal or external chemical recycling mechanisms, a "chemical conservation" campaign, and laboratory fees for…

  11. Trip Reports. Hazardous Waste Minimization and Control at Army Depots

    Science.gov (United States)

    1989-08-01

    Chief, Building 114; Major Robert Ronne; and Ken Rollins, Section Chief, Building 409. The purpose of this trip report Is to document the Information...hazardous. 6. Wf-TIM WOR Feosbility of a suitable p-etresaent f waste cuttins oil and sulleln coolant loach as 4iltratlan to remove metals. removal

  12. An Exploration of Healthcare Inventory and Lean Management in Minimizing Medical Supply Waste in Healthcare Organizations

    Science.gov (United States)

    Hicks, Rodney

    2013-01-01

    The purpose of this study was to understand how lean thinking and inventory management technology minimize expired medical supply waste in healthcare organizations. This study was guided by Toyota's theory of lean and Mintzberg's theory of management development to explain why the problem of medical supply waste exists. Government…

  13. Implementation of Waste Minimization at a complex R ampersand D site

    International Nuclear Information System (INIS)

    Lang, R.E.; Thuot, J.R.; Devgun, J.S.

    1995-01-01

    Under the 1994 Waste Minimization/Pollution Prevention Crosscut Plan, the Department of Energy (DOE) has set a goal of 50% reduction in waste at its facilities by the end of 1999. Each DOE site is required to set site-specific goals to reduce generation of all types of waste including hazardous, radioactive, and mixed. To meet these goals, Argonne National Laboratory (ANL), Argonne, IL, has developed and implemented a comprehensive Pollution Prevention/Waste Minimization (PP/WMin) Program. The facilities and activities at the site vary from research into basic sciences and research into nuclear fuel cycle to high energy physics and decontamination and decommissioning projects. As a multidisciplinary R ampersand D facility and a multiactivity site, ANL generates waste streams that are varied, in physical form as well as in chemical constituents. This in turn presents a significant challenge to put a cohesive site-wide PP/WMin Program into action. In this paper, we will describe ANL's key activities and waste streams, the regulatory drivers for waste minimization, and the DOE goals in this area, and we will discuss ANL's strategy for waste minimization and it's implementation across the site

  14. LLNL NESHAPs 2014 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bertoldo, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gallegos, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); MacQueen, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wegrecki, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-07-01

    Lawrence Livermore National Security, LLC operates facilities at Lawrence Livermore National Laboratory (LLNL) where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) National Emission Standards for Hazardous Air Pollutants (NESHAPs) in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H, which regulates radionuclide emissions to air from Department of Energy (DOE) facilities. Specifically, NESHAPs limits the emission of radionuclides to the ambient air to levels resulting in an annual effective dose equivalent of 10 mrem (100 μSv) to any member of the public. Using measured and calculated emissions, and building-specific and common parameters, LLNL personnel applied the EPA-approved computer code, CAP88-PC, Version 4.0.1.17, to calculate the dose to the maximally exposed individual member of the public for the Livermore Site and Site 300.

  15. Environmental Restoration Contractor Waste Minimization and Pollution Prevention Plan

    International Nuclear Information System (INIS)

    Duvon, D. K.

    1998-01-01

    This plan contains the Pollution Prevention (P2) Program for the Environmental Restoration Contractor (ERC). The plan outlines the activities and schedules developed by the Bechtel Hanford, Inc.(BHI) to reduce the quantity and toxicity of waste dispositioned as a result of restoration and remediation activities. The purpose of this plan is to guide ERC projects in meeting and documenting compliance with requirements for pollution prevention. This plan contains the objectives, strategy, and support activities of the ERC P2 Program

  16. LLNL Chemical Kinetics Modeling Group

    Energy Technology Data Exchange (ETDEWEB)

    Pitz, W J; Westbrook, C K; Mehl, M; Herbinet, O; Curran, H J; Silke, E J

    2008-09-24

    The LLNL chemical kinetics modeling group has been responsible for much progress in the development of chemical kinetic models for practical fuels. The group began its work in the early 1970s, developing chemical kinetic models for methane, ethane, ethanol and halogenated inhibitors. Most recently, it has been developing chemical kinetic models for large n-alkanes, cycloalkanes, hexenes, and large methyl esters. These component models are needed to represent gasoline, diesel, jet, and oil-sand-derived fuels.

  17. LLNL pure positron plasma program

    International Nuclear Information System (INIS)

    Hartley, J.H.; Beck, B.R.; Cowan, T.E.; Howell, R.H.; McDonald, J.L.; Rohatgi, R.R.; Fajans, J.; Gopalan, R.

    1995-01-01

    Assembly and initial testing of the Positron Time-of-Flight Trap at the Lawrence Livermore National Laboratory (LLNL) Increase Pulsed Positron Facility has been completed. The goal of the project is to accumulate at high-density positron plasma in only a few seconds., in order to facilitate study that may require destructive diagnostics. To date, densities of at least 6 x 10 6 positrons per cm 3 have been achieved

  18. Critical management practices influencing on-site waste minimization in construction projects.

    Science.gov (United States)

    Ajayi, Saheed O; Oyedele, Lukumon O; Bilal, Muhammad; Akinade, Olugbenga O; Alaka, Hafiz A; Owolabi, Hakeem A

    2017-01-01

    As a result of increasing recognition of effective site management as the strategic approach for achieving the required performance in construction projects, this study seeks to identify the key site management practices that are requisite for construction waste minimization. A mixed methods approach, involving field study and survey research were used as means of data collection. After confirmation of construct validity and reliability of scale, data analysis was carried out through a combination of Kruskal-Wallis test, descriptive statistics and exploratory factor analysis. The study suggests that site management functions could significantly reduce waste generation through strict adherence to project drawings, and by ensuring fewer or no design changes during construction process. Provision of waste skips for specific materials and maximisation of on-site reuse of materials are also found to be among the key factors for engendering waste minimization. The result of factor analysis suggests four factors underlying on-site waste management practices with 96.093% of total variance. These measures include contractual provisions for waste minimization, waste segregation, maximisation of materials reuse and effective logistic management. Strategies through which each of the underlying measures could be achieved are further discussed in the paper. Findings of this study would assist construction site managers and other site operatives in reducing waste generated by construction activities. Copyright © 2016 Elsevier Ltd. All rights reserved.

  19. Laboratory waste minimization during the operation startup phase

    International Nuclear Information System (INIS)

    Morrison, J.A.

    1995-05-01

    The Waste Sampling and Characterization Facility (WSCF) Laboratory was opened for occupancy in October, 1994. It is the first of its kind on the Hanford Site, a low level lab located in an area of high level radiological material. The mission of the facility is to analyze process samples from two on-line effluent treatment plants. One of these plants is operating and the other is due to begin operations by the end of 1995. The VSCF also performs air sampling analysis for routine radiological surveillance filter papers drawn from around the Hanford Site. Because this type of laboratory had not been in operation before, there was only speculation about the types and amounts of waste that would be generated. The laboratory personnel assigned to WSCF were assembled from existing labs on the Hanford Site and from outside the Hanford Site community. For some, it was a first time experience working on a site where a twenty mile drive is sometimes required to visit another building. For others, it was a change in the way business is conducted using state-of-the-art equipment, a new building, and a chance to approach issues as a team from the beginning. It is how this team came together and the issues that were discussed, sometimes uncomfortably, that lead to the current success. The outcome of this process is discussed in this paper

  20. Analysis of the matrix structure of the Nuclear Weapons Complex waste minimization and hazard reduction program

    International Nuclear Information System (INIS)

    Churnetski, S.R.

    1991-01-01

    Two of the primary goals of this program in waste minimization that the major waste problems facing the Nuclear Weapons Complex (NWC) are being addressed systematically and to prevent duplication of effort by forming an integrated approach across the complex. Production, disposal, and the hazards of both the wastes and the in-process chemicals used were to be studied. The eight waste streams chosen (electroplating, miscellaneous, mixed, plutonium, polymers, solvents, tritium, and uranium) were deemed to be the most serious problems facing the Nuclear Weapons Complex

  1. A new waste minimization method for the determination of total nonhalogenated volatile organic compounds in TRU wastes

    International Nuclear Information System (INIS)

    Sandoval, W.; Quintana, B.D.; Ortega, L.

    1997-01-01

    As part of the technical support CST-12 provides for a wide variety of defense and nondefense programs within Los Alamos National Laboratory (LANL) and the Department of Energy (DOE) complex, new waste minimization technique is under development for radiological volatile organic analysis (Hot VOA). Currently all HOT VOA must be run in a glovebox. Several types of sample contain TRU radiological waste in the form of particulates. By prefiltering the samples through a 1.2 micron syringe and counting the radioactivity, it has been found that many of the samples can be analyzed outside a glovebox. In the present investigation, the types of Hot VOA samples that can take advantage of this new technique, the volume and types of waste reduced and the experimental parameters will be discussed. Overall, the radioactive waste generated is minimized

  2. 1993 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    Kirkendall, J.R.; Engel, J.A.

    1994-01-01

    More important than waste generation numbers, the pollution prevention and waste minimization successes achieved at Hanford in 1993 have reduced waste and improved operations at the Site. Just a few of these projects are: A small research nuclear reactor, unused and destined for disposal as low level radioactive waste, was provided to a Texas University for their nuclear research program, avoiding 25 cubic meters of waste and saving $116,000. By changing the slope on a asphalt lot in front of a waste storage pad, run-off rainwater was prevented from becoming mixed low level waste water, preventing 40 cubic meters of waste and saving $750,000. Through more efficient electrostatic paint spraying equipment and a solvent recovery system, a paint shop reduced hazardous waste by 3,500 kilograms, saving $90,800. During the demolition of a large decommissioned building, more than 90% of the building's material was recycled by crushing the concrete for use on-Site and selling the steel to an off-Site recycler, avoiding a total of 12,600 metric tons of waste and saving $450,000. Additionally, several site-wide programs have avoided large quantities of waste, including the following: Through expansion of the paper and office waste recycling program which includes paper, cardboard, newspaper, and phone books, 516 metric tons of sanitary waste was reduced, saving $68,000. With the continued success of the excess chemicals program, which finds on-Site and off-Site customers for excess chemical materials, hazardous waste was reduced by 765,000 liters of liquid chemicals and 50 metric tons of solid chemicals, saving over $700,000 in disposal costs

  3. Development of a waste minimization plan for the Department of Energy's Naval petroleum reserve No. 3

    International Nuclear Information System (INIS)

    Falconer, K.L.; Lane, T.C.

    1991-01-01

    A Waste Minimization Program Plan for the U.S. Department of Energy's (DOE) Naval Petroleum Reserve No. 3 (NPR-3) was prepared in response to DOE Order 5400.1, open-quotes General Environmental Protection Program close-quote The NPR-3 Waste Minimization Program Plan encompasses all ongoing operations at the Naval Petroleum Reserve and is consistent with the principles set forth in the mission statement for NPR-3. The mission of the NPR-3 is to apply project management, engineering and scientific capabilities to produce oil and gas from subsurface zones at the maximum efficiency rate for the United States Government. NPR-3 generates more than 60 discrete waste streams, many of significant volume. Most of these waste streams are categorized as wastes from the exploration, development and production of oil and gas and, as such, are exempt from Subtitle C of RCRA as indicated in the regulatory determination published in the Federal Register on July 6, 1988. However, because so many of these waste streams contain hazardous substances and because of an increasingly more restrictive regulatory environment, in 1990 an overall effort was made to characterize all waste streams produced and institute the best waste management practice economically practical to reduce the volume and toxicity of the waste generated

  4. Minimization of municipal solid waste transportation route in West Jakarta using Tabu Search method

    Science.gov (United States)

    Chaerul, M.; Mulananda, A. M.

    2018-04-01

    Indonesia still adopts the concept of collect-haul-dispose for municipal solid waste handling and it leads to the queue of the waste trucks at final disposal site (TPA). The study aims to minimize the total distance of waste transportation system by applying a Transshipment model. In this case, analogous of transshipment point is a compaction facility (SPA). Small capacity of trucks collects the waste from waste temporary collection points (TPS) to the compaction facility which located near the waste generator. After compacted, the waste is transported using big capacity of trucks to the final disposal site which is located far away from city. Problem related with the waste transportation can be solved using Vehicle Routing Problem (VRP). In this study, the shortest distance of route from truck pool to TPS, TPS to SPA, and SPA to TPA was determined by using meta-heuristic methods, namely Tabu Search 2 Phases. TPS studied is the container type with total 43 units throughout the West Jakarta City with 38 units of Armroll truck with capacity of 10 m3 each. The result determines the assignment of each truck from the pool to the selected TPS, SPA and TPA with the total minimum distance of 2,675.3 KM. The minimum distance causing the total cost for waste transportation to be spent by the government also becomes minimal.

  5. 1994 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    1995-09-01

    Many Waste Minimization/Pollution Prevention successes at the Hanford Site occur every day without formal recognition. A few of the successful projects are: T-Plant helps facilities reuse equipment by offering decontamination services for items such as gas cylinders, trucks, and railcars, thus saving disposal and equipment replacement costs. Custodial Services reviewed its use of 168 hazardous cleaning products, and, through a variety of measures, replaced them with 38 safer substitutes, one for each task. Scrap steel contaminated with low level radioactivity from the interim stabilization of 107-K and 107-C was decontaminated and sold to a vendor for recycling. Site-wide programs include the following: the Pollution Prevention Opportunity Assessment (P2OA) program at the Hanford site was launched during 1994, including a training class, a guidance document, technical assistance, and goals; control over hazardous materials purchased was achieved by reviewing all purchase requisitions of a chemical nature; the Office Supply Reuse Program was established to redeploy unused or unwanted office supply items. In 1994, pollution prevention activities reduced approximately 274,000 kilograms of hazardous waste, 2,100 cubic meters of radioactive and mixed waste, 14,500,000 kilograms of sanitary waste, and 215,000 cubic meters off liquid waste and waste water. Pollution Prevention activities also saved almost $4.2 million in disposal, product, and labor costs. Overall waste generation increased in 1994 due to increased work and activity typical for a site with an environmental restoration mission. However, without any Waste Minimization/Pollution Prevention activities, solid radioactive waste generation at Hanford would have been 25% higher, solid hazardous waste generation would have been 30% higher, and solid sanitary waste generation would have been 60% higher

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

    Directory of Open Access Journals (Sweden)

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

    2005-10-01

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

  7. An analysis of radioactive waste minimization efforts at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Voit, S.L.; Boerigter, S.T.

    1997-09-30

    LANL will be the primary DOE facility for plutonium research and development and plutonium processing. A summary of the currently generated waste types, volumes, generating facilities or programs, and disposal costs are given in this report along with future waste generation projections. Several key existing technologies have been identified that could be introduced to reduce the generated waste at LANL. Four of these are discussed in detail in this report: (1) electrolytic surface decontamination, (2) electrochemical treatment of mixed wastes, (3) Long Range Alpha Detection (LRAD), and (4) Segmented Gate and Containerized Vat Leach System (SGS/CVL). These technologies may be implemented as modifications in upstream processes as well as more efficient volume reduction and segregation. The four technologies are mature enough to be implemented in the next two to three years and can be done so with the support for capital and operational costs. Also discussed in this report is a small sample of some of the recent waste minimization success stories that have been implemented. Several technologies are presented that are either currently being investigated or on hold due to lack of funding at LANL but show potential for making significant gains in waste minimization. This report is intended to provide a review of the waste minimization issues and analysis of the impact of implementing a few of these technologies.

  8. Minimally processed beetroot waste as an alternative source to obtain functional ingredients.

    Science.gov (United States)

    Costa, Anne Porto Dalla; Hermes, Vanessa Stahl; Rios, Alessandro de Oliveira; Flôres, Simone Hickmann

    2017-06-01

    Large amounts of waste are generated by the minimally processed vegetables industry, such as those from beetroot processing. The aim of this study was to determine the best method to obtain flour from minimally processed beetroot waste dried at different temperatures, besides producing a colorant from such waste and assessing its stability along 45 days. Beetroot waste dried at 70 °C originates flour with significant antioxidant activity and higher betalain content than flour produced from waste dried at 60 and 80 °C, while chlorination had no impact on the process since microbiological results were consistent for its application. The colorant obtained from beetroot waste showed color stability for 20 days and potential antioxidant activity over the analysis period, thus it can be used as a functional additive to improve nutritional characteristics and appearance of food products. These results are promising since minimally processed beetroot waste can be used as an alternative source of natural and functional ingredients with high antioxidant activity and betalain content.

  9. An analysis of radioactive waste minimization efforts at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Voit, S.L.; Boerigter, S.T.

    1997-01-01

    LANL will be the primary DOE facility for plutonium research and development and plutonium processing. A summary of the currently generated waste types, volumes, generating facilities or programs, and disposal costs are given in this report along with future waste generation projections. Several key existing technologies have been identified that could be introduced to reduce the generated waste at LANL. Four of these are discussed in detail in this report: (1) electrolytic surface decontamination, (2) electrochemical treatment of mixed wastes, (3) Long Range Alpha Detection (LRAD), and (4) Segmented Gate and Containerized Vat Leach System (SGS/CVL). These technologies may be implemented as modifications in upstream processes as well as more efficient volume reduction and segregation. The four technologies are mature enough to be implemented in the next two to three years and can be done so with the support for capital and operational costs. Also discussed in this report is a small sample of some of the recent waste minimization success stories that have been implemented. Several technologies are presented that are either currently being investigated or on hold due to lack of funding at LANL but show potential for making significant gains in waste minimization. This report is intended to provide a review of the waste minimization issues and analysis of the impact of implementing a few of these technologies

  10. Potential pollution prevention and waste minimization for Department of Energy operations

    International Nuclear Information System (INIS)

    Griffin, J.; Ischay, C.; Kennicott, M.; Pemberton, S.; Tull, D.

    1995-10-01

    With the tightening of budgets and limited resources, it is important to ensure operations are carried out in a cost-effective and productive manner. Implementing an effective Pollution Prevention strategy can help to reduce the costs of waste management and prevent harmful releases to the environment. This document provides an estimate of the Department of Energy's waste reduction potential from the implementation of Pollution Prevention opportunities. A team of Waste Minimization and Pollution Prevention professionals was formed to collect the data and make the estimates. The report includes a list of specific reduction opportunities for various waste generating operations and waste types. A generic set of recommendations to achieve these reduction opportunities is also provided as well as a general discussion of the approach and assumptions made for each waste generating operation

  11. Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

    Energy Technology Data Exchange (ETDEWEB)

    Lebel, A. [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A. [Raveh Ecology Ltd., Haifa (Israel)

    1993-12-31

    This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

  12. Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

    Energy Technology Data Exchange (ETDEWEB)

    Lebel, A [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A [Raveh Ecology Ltd., Haifa (Israel)

    1994-12-31

    This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

  13. Uranium Mill Tailings remedial action project waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    1994-07-01

    The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases

  14. LLNL Compliance Plan for TRUPACT-2 Authorized Methods for Payload Control

    International Nuclear Information System (INIS)

    1995-03-01

    This document describes payload control at LLNL to ensure that all shipments of CH-TRU waste in the TRUPACT-II (Transuranic Package Transporter-II) meet the requirements of the TRUPACT-II SARP (safety report for packaging). This document also provides specific instructions for the selection of authorized payloads once individual payload containers are qualified for transport. The physical assembly of the qualified payload and operating procedures for the use of the TRUPACT-II, including loading and unloading operations, are described in HWM Procedure No. 204, based on the information in the TRUPACT-II SARP. The LLNL TRAMPAC, along with the TRUPACT-II operating procedures contained in HWM Procedure No. 204, meet the documentation needs for the use of the TRUPACT-II at LLNL. Table 14-1 provides a summary of the LLNL waste generation and certification procedures as they relate to TRUPACT-II payload compliance

  15. 2016 LLNL Nuclear Forensics Summer Program

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, Mavrik [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-11-15

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Program is designed to give graduate students an opportunity to come to LLNL for 8–10 weeks for a hands-on research experience. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students also have the opportunity to meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  16. 2017 LLNL Nuclear Forensics Summer Internship Program

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, Mavrik [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-12-13

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Internship Program (NFSIP) is designed to give graduate students an opportunity to come to LLNL for 8-10 weeks of hands-on research. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students can also meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  17. 2016 LLNL Nuclear Forensics Summer Program

    International Nuclear Information System (INIS)

    Zavarin, Mavrik

    2016-01-01

    The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Program is designed to give graduate students an opportunity to come to LLNL for 8-10 weeks for a hands-on research experience. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students also have the opportunity to meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry), and gain a better understanding of the various science programs at LLNL.

  18. Identifying industrial best practices for the waste minimization of low-level radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Levin, V.

    1996-04-01

    In US DOE, changing circumstances are affecting the management and disposal of solid, low-level radioactive waste (LLW). From 1977 to 1991, the nuclear power industry achieved major reductions in solid waste disposal, and DOE is interested in applying those practices to reduce solid waste at DOE facilities. Project focus was to identify and document commercial nuclear industry best practices for radiological control programs supporting routine operations, outages, and decontamination and decommissioning activities. The project team (DOE facility and nuclear power industry representatives) defined a Work Control Process Model, collected nuclear power industry Best Practices, and made recommendations to minimize LLW at DOE facilities.

  19. An operational waste minimization chargeback system at Sandia National Laboratories, New Mexico

    International Nuclear Information System (INIS)

    Horak, K.; Peek, D.W.; Stermer, D.; Dailleboust, L.; Reilly, H.

    1993-01-01

    Sandia National Laboratories, New Mexico, (SNL/NM) has made a commitment to achieve significant reductions in the amount of hazardous wastes generated throughout its operations. The success of the SNL/NM Waste Minimization/Pollution Prevention Program depends primarily on: (1) adequate program funding, and (2) comprehensive collection and dissemination of information pertaining to SNL/NM's waste. This paper describes the chargeback system that SNL/NM has chosen for funding the implementation of the Waste Minimization/Pollution Prevention program, as well as the waste reporting system that follows naturally from the chargeback system. Both the chargeback and reporting systems have been fully implemented. The details of implementation are discussed, including: the physical means by which waste is managed and data collected; the database systems which have been linked; the flow of data through both human hands and electronic systems; the quality assurance of that data; and the waste report format now in use. Also discussed are intended improvements in the system that are currently planned for the coming years

  20. Utilizing environmental management information systems to monitor chemical usage and facilitate waste minimization

    Energy Technology Data Exchange (ETDEWEB)

    Blazer, T.L.; Kinney, R.W. [Modern Technologies Corporation, Dayton, OH (United States)

    1996-10-01

    Waste minimization and pollution prevention activities have proven to be valuable to the chemical industry`s and the chemical user`s bottom line. Many companies have found that, with a modest initial capital investment and product modifications, mounds of bureaucratic liability can be removed and substantial cost savings can be realized.

  1. Minimizing Characterization - Derived Waste at the Department of Energy Savannah River Site, Aiken, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

    Van Pelt, R. S.; Amidon, M. B.; Reboul, S. H.

    2002-02-25

    Environmental restoration activities at the Department of Energy Savannah River Site (SRS) utilize innovative site characterization approaches and technologies that minimize waste generation. Characterization is typically conducted in phases, first by collecting large quantities of inexpensive data, followed by targeted minimally invasive drilling to collect depth-discrete soil/groundwater data, and concluded with the installation of permanent multi-level groundwater monitoring wells. Waste-reducing characterization methods utilize non-traditional drilling practices (sonic drilling), minimally intrusive (geoprobe, cone penetrometer) and non-intrusive (3-D seismic, ground penetration radar, aerial monitoring) investigative tools. Various types of sensor probes (moisture sensors, gamma spectroscopy, Raman spectroscopy, laser induced and X-ray fluorescence) and hydrophobic membranes (FLUTe) are used in conjunction with depth-discrete sampling techniques to obtain high-resolution 3-D plume profiles. Groundwater monitoring (short/long-term) approaches utilize multi-level sampling technologies (Strata-Sampler, Cone-Sipper, Solinst Waterloo, Westbay) and low-cost diffusion samplers for seepline/surface water sampling. Upon collection of soil and groundwater data, information is portrayed in a Geographic Information Systems (GIS) format for interpretation and planning purposes. At the SRS, the use of non-traditional drilling methods and minimally/non intrusive investigation approaches along with in-situ sampling methods has minimized waste generation and improved the effectiveness and efficiency of characterization activities.

  2. Minimizing Characterization - Derived Waste at the Department of Energy Savannah River Site, Aiken, South Carolina

    International Nuclear Information System (INIS)

    Van Pelt, R. S.; Amidon, M. B.; Reboul, S. H.

    2002-01-01

    Environmental restoration activities at the Department of Energy Savannah River Site (SRS) utilize innovative site characterization approaches and technologies that minimize waste generation. Characterization is typically conducted in phases, first by collecting large quantities of inexpensive data, followed by targeted minimally invasive drilling to collect depth-discrete soil/groundwater data, and concluded with the installation of permanent multi-level groundwater monitoring wells. Waste-reducing characterization methods utilize non-traditional drilling practices (sonic drilling), minimally intrusive (geoprobe, cone penetrometer) and non-intrusive (3-D seismic, ground penetration radar, aerial monitoring) investigative tools. Various types of sensor probes (moisture sensors, gamma spectroscopy, Raman spectroscopy, laser induced and X-ray fluorescence) and hydrophobic membranes (FLUTe) are used in conjunction with depth-discrete sampling techniques to obtain high-resolution 3-D plume profiles. Groundwater monitoring (short/long-term) approaches utilize multi-level sampling technologies (Strata-Sampler, Cone-Sipper, Solinst Waterloo, Westbay) and low-cost diffusion samplers for seepline/surface water sampling. Upon collection of soil and groundwater data, information is portrayed in a Geographic Information Systems (GIS) format for interpretation and planning purposes. At the SRS, the use of non-traditional drilling methods and minimally/non intrusive investigation approaches along with in-situ sampling methods has minimized waste generation and improved the effectiveness and efficiency of characterization activities

  3. Laser wakefields at UCLA and LLNL

    International Nuclear Information System (INIS)

    Mori, W.B.; Clayton, C.E.; Joshi, C.; Dawson, J.M.; Decker, C.B.; Marsh, K.; Katsouleas, T.; Darrow, C.B.; Wilks, S.C.

    1991-01-01

    The authors report on recent progress at UCLA and LLNL on the nonlinear laser wakefield scheme. They find advantages to operating in the limit where the laser pulse is narrow enough to expel all the plasma electrons from the focal region. A description of the experimental program for the new short pulse 10 TW laser facility at LLNL is also presented

  4. Develop of a model to minimize and to treat waste coming from the chemical laboratories

    International Nuclear Information System (INIS)

    Chacon Hernandez, M.

    2000-01-01

    They were investigated and proposed alternative of minimization and treatment of waste organic type coming from chemical laboratories, considering as alternative the disposition for the drainage, the chemical treatment of the waste, the disposition in sanitary fillers, the creation of a cellar to recycle material, the incineration, the distillation and the possibility to establish an agreement with the company Cements INCSA to discard the materials in the oven to cements of this enterprise. the methodology had as first stage the summary of information about the production of residuals for Investigation Center or Academic Unit. For this they were considered the laboratories of investigation of the CICA, CELEQ, CIPRONA, LAYAFA, and the laboratories of teaching of the sections of Organic Chemistry, Inorganic Chemistry, Physicochemical, Pharmacognosy, Drugs Analysis, Physicopharmacy, Histology and Physiology. Additionally, you considers the office of purveyor of the Microbiology School. Subsequently one carries out an analysis of costs to determine which waste constituted most of the waste generated by the University, as for cost and volume. Then, they were carried out classifications of the materials according to chemical approaches, classification of the NFPA and for data of combustion heats. Once carried out this classification and established the current situation of the laboratories considered as for handling and treatment of waste, they proceeded to evaluate and select treatment options and disposition of waste considering advantages and disadvantages as for implementation possibility and cost stops this way a minimization model and treatment that it can be implemented in the University to settle down [es

  5. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, P. M.

    2013-02-21

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

  6. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  7. Waste minimization, recycling and reuse in operations support services fleet maintenance

    International Nuclear Information System (INIS)

    Trego, A.L.

    1994-01-01

    Government regulations and smart business practices demand that organizations dramatically reduce both the type and volume of waste generated by their operations. This article describes successful waste minimization and recycling programs created by the Fleet Maintenance, Operations Support Services Division, Westinghouse Hanford Company. These comprehensive programs have greatly reduced waste formerly produced in maintaining 3,528 government-owned vehicles and nearly 200 emergency power generators at the Hanford Site. The actions are integral to preventing future contamination of the Site as well as to cleaning up the complexity of wastes from almost 50 years of defense production. The results of the Fleet Maintenance programs are impressive, recording cost savings of $290,000 in fiscal year 1993 and $965,000 since 1988

  8. Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    Hartnett, S.; Seguin, N.; Burns, M.

    1995-01-01

    The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned

  9. WESF hot cells waste minimization criteria hot cells window seals evaluation

    International Nuclear Information System (INIS)

    Walterskirchen, K.M.

    1997-01-01

    WESF will decouple from B Plant in the near future. WESF is attempting to minimize the contaminated solid waste in their hot cells and utilize B Plant to receive the waste before decoupling. WESF wishes to determine the minimum amount of contaminated waste that must be removed in order to allow minimum maintenance of the hot cells when they are placed in ''laid-up'' configuration. The remaining waste should not cause unacceptable window seal deterioration for the remaining life of the hot cells. This report investigates and analyzes the seal conditions and hot cell history and concludes that WESF should remove existing point sources, replace cerium window seals in F-Cell and refurbish all leaded windows (except for A-Cell). Work should be accomplished as soon as possible and at least within the next three years

  10. Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Hartnett, S.; Seguin, N. [Benchmark Environmental Corp., Albuquerque, NM (United States); Burns, M. [Los Alamos National Lab., NM (United States)

    1995-12-31

    The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

  11. Pollution prevention/waste minimization program 1998 fiscal year work plan - WBS 1.11.2.1

    International Nuclear Information System (INIS)

    Howald, S.C.; Merry, D.S.

    1997-09-01

    Pollution Prevention/Waste Minimization (P2/WMin) is the Department of Energy's preferred approach to environmental management. The P2/WMin mission is to eliminate or minimize waste generation, pollutant releases to the environment, use of toxic substances, and to conserve resources by implementing cost-effective pollution prevention technologies, practices, and polices

  12. Unrestricted disposal of minimal activity levels of radioactive wastes: exposure and risk calculations

    International Nuclear Information System (INIS)

    Fields, D.E.; Emerson, C.J.

    1984-08-01

    The US Nuclear Regulatory Commission is currently considering revision of rule 10 CFR Part 20, which covers disposal of solid wastes containing minimal radioactivity. In support of these revised rules, we have evaluated the consequences of disposing of four waste streams at four types of disposal areas located in three different geographic regions. Consequences are expressed in terms of human exposures and associated health effects. Each geographic region has its own climate and geology. Example waste streams, waste disposal methods, and geographic regions chosen for this study are clearly specified. Monetary consequences of minimal activity waste disposal are briefly discussed. The PRESTO methodology was used to evaluate radionuclide transport and health effects. This methodology was developed to assess radiological impacts to a static local population for a 1000-year period following disposal. Pathways and processes of transit from the trench to exposed populations included the following considerations: groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. 12 references, 2 figures, 8 tables

  13. Annual Waste Minimization Summary Report for the National Nuclear Security Administration Nevada Site Office

    International Nuclear Information System (INIS)

    Alfred J. Karns

    2007-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U. S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during CY06. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit ((number s ign)NEV HW0021) and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the DOE, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  14. Environmental Restoration Contractor Waste Minimization and Pollution Prevention Plan. Revision 1

    International Nuclear Information System (INIS)

    Lewis, R.A.

    1996-03-01

    This plan contains the Environmental Restoration Contractor (ERC) Waste Minimization and Pollution Prevention (WMin/P2) Program. The plan outlines the activities and schedules developed by the ERC to reduce the quantity and toxicity of waste dispositioned as a result of restoration and remediation activities. This plan satisfies US Department of Energy (DOE) requirements including the Pollution Prevention Awareness program required by DOE Order 5400.1 (DOE 1988). This plan is consistent with Executive Order 12856 and Secretary O'Leary's pollution prevention Policy Statement of December 27, 1994, which set US and DOE pollution prevention policies, respectively. It is also consistent with the DOE Pollution Prevention Crosscut Plan, 1994, which provides guidance in meeting the DOE goals in pollution prevention. The purpose of this plan is to aid ERC projects in meeting and documenting compliance with requirements for WMin/P2. This plan contains the objectives, strategy, and support activities of the ERC Team WMin/P2 program. The basic elements of the plan are pollution prevention goals, waste assessments of major waste streams, implementation of feasible waste minimization opportunities, and a process for reporting achievements. Wherever appropriate, the ERC will integrate the pollution prevention activities in this plan into regular program activities rather than establishing separate WMin/P2 activities. Moreover, wherever possible, existing documents, procedures, and activities will be used to meet WMin/P2 requirements

  15. Development of waste minimization and decontamination technologies at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Ferguson, R.L.; Archibald, K.E.; Demmer, R.L.

    1995-01-01

    Emphasis on the minimization of decontamination secondary waste has increased because of restrictions on the use of hazardous chemicals and Idaho Chemical Processing Plant (ICPP) waste handling issues. The Lockheed Idaho Technologies Co. (LITCO) Decontamination Development Subunit has worked to evaluate and introduce new performed testing, evaluations, development and on-site demonstrations for a number of novel decontamination techniques that have not yet previously been used at the ICPP. This report will include information on decontamination techniques that have recently been evaluated by the Decontamination Development Subunit

  16. Application of geographic information systems to waste minimization efforts at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Lyttle, T.W.; Smith, D.M.; Burns, M.; Weinrach, J.B.

    1993-01-01

    At Los Alamos National Laboratory (LANL), facility waste streams tend to be small but highly diverse. Initial characterization of such waste streams is often difficult in part due to a lack of tools to assist the generators themselves in completing such assessments. A methodology has been developed at LANL to allow process knowledgeable field personnel to develop baseline waste generation assessments and to evaluate potential waste minimization technology. This Process Waste Assessment (PWA) system is an application constructed within the Process Modeling System and currently being integrated with the InFoCAD Geographic Information System (GIS) . The Process Modeling System (PMS) is an object-oriented, mass balance-based, discrete-event simulation framework written using the Common Lisp Object System (CLOS) . Analytical capabilities supported within the PWA system include: complete mass balance specifications, historical characterization of selected waste streams and generation of facility profiles for materials consumption, resource utilization and worker exposure. Development activities include integration with the LANL facilities management Geographic Information System (GIS) and provisions for a Best Available Technologies (BAT) database. The environments used to develop these assessment tools will be discussed in addition to a review of initial implementation results

  17. Application of geographic information systems to waste minimization efforts at the national laboratories

    International Nuclear Information System (INIS)

    Lyttle, T.W.; Smith, D.M.; Burns, M.; Weinrach, J.B.

    1993-01-01

    At Los Alamos National Laboratory (LANL), facility waste streams tend to be small but highly diverse. Initial characterization of such waste streams is often difficult in part due to a lack of tools to assist the generators themselves in completing such assessments. A methodology has been developed at LANL to allow process knowledgeable field personnel to develop baseline waste generation assessments and to evaluate potential waste minimization technology. This Process Waste Assessment (PWA) system is an application constructed within the Process Modeling System and currently being integrated with the InFoCAD Geographic Information System (GIS). The Process Modeling System (PMS) is an object-oriented, mass balance-based, discrete-event simulation framework written using the Common Lisp Object System (CLOS). Analytical capabilities supported within the PWA system include: complete mass balance specifications, historical characterization of selected waste stream and generation of facility profiles for materials consumption, resource utilization and worker exposure. Development activities include integration with the LANL facilities management Geographic Information System (GIS) and provisions for a Best Available Technologies (BAT) database. The environments used to develop these assessment tools will be discussed in addition to a review of initial implementation results

  18. On the technical development to minimize the quantity of solid wastes in a uranium conversion

    International Nuclear Information System (INIS)

    Otomura, Keiichiro; Ogura, Yoshikazu; Fujisaki, Sakae

    1987-01-01

    We have developed the new process of treating the waste liquor from a uranium conversion at Ningyo Toge Works PNC, Japan. This process consists of neutralizing precipitation, solid liquid separation, distillation and adsorption. At a neutralizing precipitation step a magnesium oxide is added in the waste liquor containing uranium and fluorine. Most of the uranium and fluorine in the waste liquor precipitate as magnesium compounds. A sulfuric acid is added to the precipitate separated by a filter to dissolve. The resulting solution is then distilled to recover a hydrofluoric acid as a distillate. Uranium is recovered from a residue by an anion exchange method. The recoverd fluorine and uranium are recycled to the main process of conversion. The filtrate separated at the precipitation step is then passed through adsorbing columns. The residual fluorine and uranium in the filtrate were adsorbed and removed by the chelating resine which selectively adsorb the uranium and fluorine. After that the treated waste liquor is discharged out of the plant. This process has merits of being able to minimize the quantity of solid waste in comparison with the conventional process and to recover uranium and fluorine. This process can also be applied to uranium reconversion process from uranium hexafluoride to uranium oxide and to uranium metal production process, which produce the same kind of waste liquor. (author)

  19. Waste minimization assessment for a manufacturer of baseball bats and golf clubs. Environmental research brief

    Energy Technology Data Exchange (ETDEWEB)

    Fleischman, M.; Kirsch, F.W.; Maginn, J.C.

    1993-09-01

    The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small and medium-size manufacturers who want to minimize their generation of waste but who lack the expertise to do so. Waste Minimization Assessment Center (WMAC) at the University of Louisville performed an assessment at a plant manufacturing baseball bats and golf clubs -- approximately 1,500,000 bats/yr and 550,000 golf clubs/yr. To make the bats, wood billets are oven-dried and machined to a standard dimension. After sanding they are branded and finished. The golf clubs are made by finishing and assembling purchased heads and shafts. The team's report detailing findings and recommendations, indicated that the most waste, other than rinse water discharged to the publicly owned treatment works (POTW) and wood turnings which are sold, consists of scrap cardboard and paper from the shop and offices, and that the greatest savings, including new income, could be obtained by segregating the cardboard and paper wastes for sale to a local recycler.

  20. Fire science at LLNL: A review

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, H.K. (ed.)

    1990-03-01

    This fire sciences report from LLNL includes topics on: fire spread in trailer complexes, properties of welding blankets, validation of sprinkler systems, fire and smoke detectors, fire modeling, and other fire engineering and safety issues. (JEF)

  1. 1994 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1

    International Nuclear Information System (INIS)

    Irwin, E.F.; Poligone, S.E.

    1995-01-01

    The Y-12 Plant serves as a key manufacturing technology center for the development and demonstration of unique materials, components, and services of importance to the Department of Energy (DOE) and the nation. This is accomplished through the reclamation and storage of nuclear materials, manufacture of nuclear materials, manufacture of components for the nation's defense capabilities, support to national security programs, and services provided to other customers as approved by DOE. We are recognized by our people, the community, and our customers as innovative, responsive, and responsible. We are a leader in worker health and safety, environmental protection, and stewardship of our national resources. As a DOE facility, Y-12 also supports DOE's waste minimization mission. Data contained in this report represents waste generation in Tennessee

  2. WARRP Decon-13: Subject Matter Expert (SME) Meeting Waste Screening and Waste Minimization Methodologies Project

    Science.gov (United States)

    2012-08-01

    media (e.g., zeolites ) that have been used to try to remove radionuclides from water that is being released to the ocean. Mr. Tupin stated...a wide-area RDD incident. The results from the SME Meeting were used to prepare a draft SOF to focus specifically on systems for waste segregation...Protection Agency (EPA), the U.S. Department of Defense (DoD), the U.S. Department of Energy (DOE), the U.S. Department of Health and Human Services (HHS

  3. Standard data report. 1997 annual report on waste generation and waste minimization progress

    International Nuclear Information System (INIS)

    Wilburn, D.

    1998-01-01

    The Laboratory's central mission of Reducing the Global Nuclear Danger supports core competencies that enable the Laboratory to contribute to defense, civilian, and industrial needs. In turn, the intellectual challenges of civilian and industrial problems strengthen and help support the core competencies required for the national security mission. The ability to do great science underpins all of the applied work. There are five core competencies which support this mission: (1) Stockpile Stewardship ensures the US has safe, secure and reliable nuclear weapons; (2) Stockpile Management provides capabilities ranging from dismantling to remanufacturing of the enduring stockpile; (3) Nuclear Materials Management ensures the availability and safe disposition of plutonium, highly enriched uranium, and tritium; (4) Nonproliferation and Counterproliferation help to deter, detect, and respond to the proliferation of weapons of mass destruction; and (5) Environmental Stewardship provides for the remediation and reduction of wastes from the nuclear weapons complex. This report contains data on volumes of waste generated as part of routine and cleanup/stabilization activities of the lab

  4. LLNL's Regional Seismic Discrimination Research

    International Nuclear Information System (INIS)

    Hanley, W; Mayeda, K; Myers, S; Pasyanos, M; Rodgers, A; Sicherman, A; Walter, W

    1999-01-01

    As part of the Department of Energy's research and development effort to improve the monitoring capability of the planned Comprehensive Nuclear-Test-Ban Treaty international monitoring system, Lawrence Livermore Laboratory (LLNL) is testing and calibrating regional seismic discrimination algorithms in the Middle East, North Africa and Western Former Soviet Union. The calibration process consists of a number of steps: (1) populating the database with independently identified regional events; (2) developing regional boundaries and pre-identifying severe regional phase blockage zones; (3) measuring and calibrating coda based magnitude scales; (4a) measuring regional amplitudes and making magnitude and distance amplitude corrections (MDAC); (4b) applying the DOE modified kriging methodology to MDAC results using the regionalized background model; (5) determining the thresholds of detectability of regional phases as a function of phase type and frequency; (6) evaluating regional phase discriminant performance both singly and in combination; (7) combining steps 1-6 to create a calibrated discrimination surface for each stations; (8) assessing progress and iterating. We have now developed this calibration procedure to the point where it is fairly straightforward to apply earthquake-explosion discrimination in regions with ample empirical data. Several of the steps outlined above are discussed in greater detail in other DOE papers in this volume or in recent publications. Here we emphasize the results of the above process: station correction surfaces and their improvement to discrimination results compared with simpler calibration methods. Some of the outstanding discrimination research issues involve cases in which there is little or no empirical data. For example in many cases there is no regional nuclear explosion data at IMS stations or nearby surrogates. We have taken two approaches to this problem, first finding and using mining explosion data when available, and

  5. LLNL Site 200 Risk Management Plan

    International Nuclear Information System (INIS)

    Pinkston, D.; Johnson, M.

    2008-01-01

    It is the Lawrence Livermore National Laboratory's (LLNL) policy to perform work in a manner that protects the health and safety of employees and the public, preserves the quality of the environment, and prevents property damage using the Integrated Safety Management System. The environment, safety, and health are to take priority in the planning and execution of work activities at the Laboratory. Furthermore, it is the policy of LLNL to comply with applicable ES and H laws, regulations, and requirements (LLNL Environment, Safety and Health Manual, Document 1.2, ES and H Policies of LLNL). The program and policies that improve LLNL's ability to prevent or mitigate accidental releases are described in the LLNL Environment, Health, and Safety Manual that is available to the public. The laboratory uses an emergency management system known as the Incident Command System, in accordance with the California Standardized Emergency Management System (SEMS) to respond to Operational Emergencies and to mitigate consequences resulting from them. Operational Emergencies are defined as unplanned, significant events or conditions that require time-urgent response from outside the immediate area of the incident that could seriously impact the safety or security of the public, LLNL's employees, its facilities, or the environment. The Emergency Plan contains LLNL's Operational Emergency response policies, commitments, and institutional responsibilities for managing and recovering from emergencies. It is not possible to list in the Emergency Plan all events that could occur during any given emergency situation. However, a combination of hazard assessments, an effective Emergency Plan, and Emergency Plan Implementing Procedures (EPIPs) can provide the framework for responses to postulated emergency situations. Revision 7, 2004 of the above mentioned LLNL Emergency Plan is available to the public. The most recent revision of the LLNL Emergency Plan LLNL-AM-402556, Revision 11, March

  6. Knowledge-based and model-based hybrid methodology for comprehensive waste minimization in electroplating plants

    Science.gov (United States)

    Luo, Keqin

    1999-11-01

    The electroplating industry of over 10,000 planting plants nationwide is one of the major waste generators in the industry. Large quantities of wastewater, spent solvents, spent process solutions, and sludge are the major wastes generated daily in plants, which costs the industry tremendously for waste treatment and disposal and hinders the further development of the industry. It becomes, therefore, an urgent need for the industry to identify technically most effective and economically most attractive methodologies and technologies to minimize the waste, while the production competitiveness can be still maintained. This dissertation aims at developing a novel WM methodology using artificial intelligence, fuzzy logic, and fundamental knowledge in chemical engineering, and an intelligent decision support tool. The WM methodology consists of two parts: the heuristic knowledge-based qualitative WM decision analysis and support methodology and fundamental knowledge-based quantitative process analysis methodology for waste reduction. In the former, a large number of WM strategies are represented as fuzzy rules. This becomes the main part of the knowledge base in the decision support tool, WMEP-Advisor. In the latter, various first-principles-based process dynamic models are developed. These models can characterize all three major types of operations in an electroplating plant, i.e., cleaning, rinsing, and plating. This development allows us to perform a thorough process analysis on bath efficiency, chemical consumption, wastewater generation, sludge generation, etc. Additional models are developed for quantifying drag-out and evaporation that are critical for waste reduction. The models are validated through numerous industrial experiments in a typical plating line of an industrial partner. The unique contribution of this research is that it is the first time for the electroplating industry to (i) use systematically available WM strategies, (ii) know quantitatively and

  7. The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

    International Nuclear Information System (INIS)

    Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

    1992-01-01

    A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

  8. Development of a methodology for minimizing 241Am waste from radioactive lightning rod

    International Nuclear Information System (INIS)

    Araujo, Valeska Peres de; Sousa, Alvaro S.F. de; Ferreira, Elizabeth de M.M.; Brandao, Luis Eduardo Barreira

    2011-01-01

    In 1989, the Brazilian National Nuclear Energy Commission, CNEN, cancelled the authorization to produce and install lightning rods that employed radioisotopes sources, which since then have been collected and treated as radioactive waste. The main radioisotopes employed as a radioactive source onto the lightning rods were the 241 Am and 226 Ra, being the 241 Am the most used due to its lower production cost. In the radioactive lightning rods the sources are first fixed in a stainless steel support, then sealed and fixed on the 30 cm length lightning rod body by rivets. These captors when constantly exposed to rain and winds can release the radioactive material and then contaminate the device, generating a greater volume of waste.The focus of this preliminary study is to develop a methodology to minimize the final volume of waste by removing the source followed by a chemical treatment to clean the lightning rods. Ultrasound techniques associated with suitable solvents as water, acids and chelates was applied. Gamma spectrometry was used to analyze the material after each decontamination step. In agreement to Regulations of Radiological Protection, the results indicate that it is possible to dispose of the lightning rod after the source removal followed by a suitable treatment and reducing this way the volume of waste. (author)

  9. Exposure and risk calculations for disposal of wastes having minimal radioactivity

    International Nuclear Information System (INIS)

    Fields, D.E.

    1984-01-01

    The US Nuclear Regulatory Commission is currently considering revision of rules 10 CFR 20 and 10 CFR 61, which cover disposal of solid wastes containing minimal activity radioactivity. In support of these revised rules, we have evaluated the consequences of disposing of four waste streams at four types of disposal areas located in three different geographic regions. Consequences are expressed in terms of human exposures and associated health effects. Each geographic region has its own climate and geology. Example waste streams, waste disposal methods, and geographic regions chosen for this study are clearly specified. The PRESTO-II methodology was used to evaluate radionuclide transport and health effects. This methodology was developed to assess radiological impacts to a static local population for a 1000-year period following disposal. The modeling of pathways and processes of migration from the trench to exposed populations included the following considerations: groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. 9 references, 2 figures, 3 tables

  10. Cost/benefit analysis for selected waste minimization technologies at TA-55

    International Nuclear Information System (INIS)

    Boerigter, S.T.

    1996-01-01

    The TA-55 plutonium facility at LANL is one of the remaining plutonium-handling facilities in the United States with significant operational capability. In recent years a great deal of attention has been focused on the waste streams generated by this facility. Costs of properly treating these streams have risen significantly. This paper discusses the characterization of several proposed radioactive waste minimization technologies as a function of Return on Investment (ROI). In particular, the DOE Environmental Management program has identified a specific funding channel for such technology development activities, but this funding channel requires a restrictive definition of ROI. Here, a simple extension to the required ROI equation is used to capture the lifecycle ROI due to offsets in future capital charges resulting from present spending

  11. Waste processing plant eco-auditing system for minimization of environmental risk: European Communities regulatory proposal

    International Nuclear Information System (INIS)

    Brunetti, N.

    1993-01-01

    This paper delineates a system of process control and monitoring checks to be applied to municipal-industrial waste processing and disposal plants to ensure their energy efficient, environmentally safe and reliable operation. In line with European Communities environmental protection strategies, this eco-auditing system requires the preparation of environmental impacts statements on a regular basis during plant operation, as well as, prior to plant start-up. Continuous plant environmental compatibility evaluations are to ascertain: material and energy inputs and outputs; the composition and amounts of exhaust gases released into the atmosphere and the integrity of treatment liquids; control and monitoring instrumentation reliability. The implementation of the auditing system is to be carried out under the supervision of authorized auditing personnel. Waste processing and disposal plants are to make maximum use of energy and materials recovery processes so as to minimize energy consumption and risk to the environment

  12. FY16 LLNL Omega Experimental Programs

    International Nuclear Information System (INIS)

    Heeter, R. F.; Ali, S. J.; Benstead, J.; Celliers, P. M.; Coppari, F.; Eggert, J.; Erskine, D.; Panella, A. F.; Fratanduono, D. E.; Hua, R.; Huntington, C. M.; Jarrott, L. C.; Jiang, S.; Kraus, R. G.; Lazicki, A. E.; LePape, S.; Martinez, D. A.; McNaney, J. M.; Millot, M. A.; Moody, J.; Pak, A. E.; Park, H. S.; Ping, Y.; Pollock, B. B.; Rinderknecht, H.; Ross, J. S.; Rubery, M.; Sio, H.; Smith, R. F.; Swadling, G. F.; Wehrenberg, C. E.; Collins, G. W.; Landen, O. L.; Wan, A.; Hsing, W.

    2016-01-01

    In FY16, LLNL's High-Energy-Density Physics (HED) and Indirect Drive Inertial Confinement Fusion (ICF-ID) programs conducted several campaigns on the OMEGA laser system and on the EP laser system, as well as campaigns that used the OMEGA and EP beams jointly. Overall, these LLNL programs led 430 target shots in FY16, with 304 shots using just the OMEGA laser system, and 126 shots using just the EP laser system. Approximately 21% of the total number of shots (77 OMEGA shots and 14 EP shots) supported the Indirect Drive Inertial Confinement Fusion Campaign (ICF-ID). The remaining 79% (227 OMEGA shots and 112 EP shots) were dedicated to experiments for High-Energy-Density Physics (HED). Highlights of the various HED and ICF campaigns are summarized in the following reports. In addition to these experiments, LLNL Principal Investigators led a variety of Laboratory Basic Science campaigns using OMEGA and EP, including 81 target shots using just OMEGA and 42 shots using just EP. The highlights of these are also summarized, following the ICF and HED campaigns. Overall, LLNL PIs led a total of 553 shots at LLE in FY 2016. In addition, LLNL PIs also supported 57 NLUF shots on Omega and 31 NLUF shots on EP, in collaboration with the academic community.

  13. Gunite and associated tanks remediation project recycling and waste minimization effort

    International Nuclear Information System (INIS)

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

    1998-05-01

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

  14. Minimization of waste volumes by means of pin-pointed decontamination during decommissioning measures. Final report

    International Nuclear Information System (INIS)

    Henschel, K.; Jacobs, W.; Kanitz, L.; Schildbach, T.

    1992-06-01

    This semi-automated equipment is able to remove surface building contamination as well as take radioactive measurements. This equipment is newly developed. The goal of the equipment is to improve the identification of areas of contamination and the compounding decontamination of epoxy layer building construction material by using commercially available components minimizing the waste volume. A system design for decommissioning of building surfaces was developed, selected components were tested and their function certified. With this systems concept the decontamination of fixed epoxy layers up to 20 m in height is possible. Operational data for the system are available. (orig.) [de

  15. Systematic process synthesis and design methods for cost effective waste minimization

    International Nuclear Information System (INIS)

    Biegler, L.T.; Grossman, I.E.; Westerberg, A.W.

    1995-01-01

    We present progress on our work to develop synthesis methods to aid in the design of cost effective approaches to waste minimization. Work continues to combine the approaches of Douglas and coworkers and of Grossmann and coworkers on a hierarchical approach where bounding information allows it to fit within a mixed integer programming approach. We continue work on the synthesis of reactors and of flexible separation processes. In the first instance, we strive for methods we can use to reduce the production of potential pollutants, while in the second we look for ways to recover and recycle solvents

  16. Systematic process synthesis and design methods for cost effective waste minimization

    Energy Technology Data Exchange (ETDEWEB)

    Biegler, L.T.; Grossman, I.E.; Westerberg, A.W. [Carnegie Mellon Univ., Pittsburgh, PA (United States)

    1995-12-31

    We present progress on our work to develop synthesis methods to aid in the design of cost effective approaches to waste minimization. Work continues to combine the approaches of Douglas and coworkers and of Grossmann and coworkers on a hierarchical approach where bounding information allows it to fit within a mixed integer programming approach. We continue work on the synthesis of reactors and of flexible separation processes. In the first instance, we strive for methods we can use to reduce the production of potential pollutants, while in the second we look for ways to recover and recycle solvents.

  17. Waste minimization and the goal of an environmentally benign plutonium processing facility: A strategic plan

    International Nuclear Information System (INIS)

    Pillay, K.K.S.

    1994-02-01

    To maintain capabilities in nuclear weapons technologies, the Department of Energy (DOE) has to maintain a plutonium processing facility that meets all the current and emerging standards of environmental regulations. A strategic goal to transform the Plutonium Processing Facility at Los Alamos into an environmentally benign operation is identified. A variety of technologies and systems necessary to meet this goal are identified. Two initiatives now in early stages of implementation are described in some detail. A highly motivated and trained work force and a systems approach to waste minimization and pollution prevention are necessary to maintain technical capabilities, to comply with regulations, and to meet the strategic goal

  18. Waste minimization of a process fluid through effective control under various controllers tuning

    International Nuclear Information System (INIS)

    Younas, M.; Gul, S.; Naveed, S.

    2005-01-01

    Whenever a process is disturbed either by servo system or regulatory system, the control action is applied to trace the desired point. An efficient controller setting should be selected in order to get speedy response under the pattern or constraints of quality of the product. The effective control action is desired to utilize the maximum of raw material and to minimize the waste. This is a critical problem in cases where the raw material or product is valuable and costly, e.g. pharmaceuticals. This problem has been addressed in this work on a laboratory scale plant. The plant consists of feed tank, pumps, plate and frame heat exchanger and hot water re-circulator tank. The system responses were logged with computer while the controller was tuned with Ziegler-Nichols (Z-N) and Cohen-Coon (C-C) tunings. A detailed study indicates that Ziegler-Nichols Controller tunings is better than Cohen-Coon as waste production was minimized. (author)

  19. The Research Status for Decommissioning and Radioactive Waste Minimization of HTR-PM

    International Nuclear Information System (INIS)

    Li Wenqian; Li Hong; Cao Jianzhu; Tong Jiejuan

    2014-01-01

    Decommissioning of the high-temperature gas-cooled reactor-pebble bed module (HTR-PM) as a part of the nuclear power plant, is very important during the early design stage of the construction, and it is under study and research currently. This article gives a thorough description of the current decommissioning study status of HTR-PM. Since HTR-PM has its features such as adopting a large amount of graphite, the waste inventory and characterization will be quite different from other type of reactors, new researches should be carried out and good lessons of practices and experiences should be learned from international other reactors, especially the AVR. Based on the new international regulations and Chinese laws, a comprehensive decommissioning program should be proposed to guarantee the HTR-PM will succeed in every stage of the decommissioning, such as defueling, decontamination, dismantling, demolition, waste classification and disposal, etc. In the meantime, the minimization of the radioactive waste should be taken into account during the whole process - before construction, during operation and after shut down. In this article, the decommissioning strategy and program conception of HTR-PM will be introduced, the radiation protection consideration during the decommissioning activities will be discussed, and the research on the activation problem of the decommissioning graphite will be introduced. (author)

  20. Minimizing Onsite Organic Household Left-Over Waste: The Emission Benefits of Keeping Pet Rabbits.

    Directory of Open Access Journals (Sweden)

    Konstantinos P. Tsagarakis

    2017-09-01

    Full Text Available As waste management is becoming all the more crucial, this study investigates the way in which house left-over organic waste can be better managed on site, in order to minimize the off-site treatment cost and maximize environmental performance. For the implementation of this research, a full year measurement was recorded, showing the organic leftover waste food intake of two rabbits in a household of four. The organic food, collected in two separate baskets suitable for composting—though one for rabbit intake—was 168.5 kg in total, plus 68.8 kg, which was delivered directly to the composting bin, along with food remains and rabbit feces. The results show that, over the examined year, a total of up to 0.417 metric tons of CO2 equivalent per year emissions was avoided, suggesting that if 30 houses were to apply this methodology, one garbage truck journey per year would be saved. Overall, this study suggests that better information and environmental awareness can result in on-site, low cost, individual management of recyclable organic material, which would assist with the decrease in the cost of management, along with increased environmental performance.

  1. The Los Alamos National Laboratory Chemistry and Metallurgy Research Facility upgrades project - A model for waste minimization

    International Nuclear Information System (INIS)

    Burns, M.L.; Durrer, R.E.; Kennicott, M.A.

    1996-07-01

    The Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Facility, constructed in 1952, is currently undergoing a major, multi-year construction project. Many of the operations required under this project (i.e., design, demolition, decontamination, construction, and waste management) mimic the processes required of a large scale decontamination and decommissioning (D ampersand D) job and are identical to the requirements of any of several upgrades projects anticipated for LANL and other Department of Energy (DOE) sites. For these reasons the CMR Upgrades Project is seen as an ideal model facility - to test the application, and measure the success of - waste minimization techniques which could be brought to bear on any of the similar projects. The purpose of this paper will be to discuss the past, present, and anticipated waste minimization applications at the facility and will focus on the development and execution of the project's open-quotes Waste Minimization/Pollution Prevention Strategic Plan.close quotes

  2. Implementation of Lean Warehouse to Minimize Wastes in Finished Goods Warehouse of PT Charoen Pokphand Indonesia Semarang

    Directory of Open Access Journals (Sweden)

    Nia Budi Puspitasari

    2016-03-01

    Full Text Available PT. Charoen Pokphand Indonesia Semarang is one of the largest poultry feed companies in Indonesia. To store the finished products that are ready to be distributed, it needs a finished goods warehouse. To minimize the wastes that occur in the process of warehousing the finished goods, the implementation of lean warehouse is required. The core process of finished goods warehouse is the process of putting bag that has been through the process of pallets packing, and then transporting the pallets contained bags of feed at finished goods warehouses and the process of unloading food from the finished goods warehouse to the distribution truck. With the implementation of the lean warehouse, we can know whether the activities are value added or not, to be identified later which type of waste happened. Opinions of stakeholders regarding the waste that must be eliminated first need to be determined by questionnaires. Based on the results of the questionnaires, three top wastes are selected to be identified the cause by using fishbone diagram. They can be repaired by using the implementation of 5S, namely Seiri, Seiton, Seiso, Seiketsu, and Shitsuke. Defect waste can be minimized by selecting pallet, putting sack correctly, forklift line clearance, applying working procedures, and creating cleaning schedule. Next, overprocessing waste is minimized by removing unnecessary items, putting based on the date of manufacture, and manufacture of feed plan. Inventory waste is minimized by removing junks, putting feed based on the expired date, and cleaning the barn

  3. Waste level analysis in a care section with the lean maintenance method to minimize waste in PT. Varia Usaha Beton Gresik

    Directory of Open Access Journals (Sweden)

    Rochmoeljati Rr.

    2017-06-01

    Full Text Available The major problem faced by PT. Varia Usaha Beton Gresik is not the maintenance activity according to Standard Operation Procedure (SOP, but the activities conducted without taking into account the waste. The purpose of this study is to examine the waste in the maintenance activities as to minimize it by the lean maintenance method. This is taken on a conveyor belt weigher machine, a bucket conveyor, a concrete mixer, and a machine host. The variable is the flow of treatment by reducing waste and by giving recommendation of improvement. Data collection includes damage data, production data, product disability data, and maintenance activity data. The conclusion is QT-10 waste motion machine takes 532 minutes for waste repair, 45 minutes for waste process, and 90 minutes for waste waiting. Our recommendations include improvement on the information provided, on training and rewards, and on supervisors of the production line.

  4. FY16 LLNL Omega Experimental Programs

    Energy Technology Data Exchange (ETDEWEB)

    Heeter, R. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ali, S. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Benstead, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Celliers, P. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Coppari, F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Eggert, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Erskine, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Panella, A. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fratanduono, D. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hua, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Huntington, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jarrott, L. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jiang, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kraus, R. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lazicki, A. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); LePape, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Martinez, D. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McNaney, J. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Millot, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Moody, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pak, A. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Park, H. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ping, Y. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pollock, B. B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rinderknecht, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ross, J. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rubery, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sio, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, R. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Swadling, G. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wehrenberg, C. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Collins, G. W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Landen, O. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wan, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hsing, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-12-01

    In FY16, LLNL’s High-Energy-Density Physics (HED) and Indirect Drive Inertial Confinement Fusion (ICF-ID) programs conducted several campaigns on the OMEGA laser system and on the EP laser system, as well as campaigns that used the OMEGA and EP beams jointly. Overall, these LLNL programs led 430 target shots in FY16, with 304 shots using just the OMEGA laser system, and 126 shots using just the EP laser system. Approximately 21% of the total number of shots (77 OMEGA shots and 14 EP shots) supported the Indirect Drive Inertial Confinement Fusion Campaign (ICF-ID). The remaining 79% (227 OMEGA shots and 112 EP shots) were dedicated to experiments for High-Energy-Density Physics (HED). Highlights of the various HED and ICF campaigns are summarized in the following reports. In addition to these experiments, LLNL Principal Investigators led a variety of Laboratory Basic Science campaigns using OMEGA and EP, including 81 target shots using just OMEGA and 42 shots using just EP. The highlights of these are also summarized, following the ICF and HED campaigns. Overall, LLNL PIs led a total of 553 shots at LLE in FY 2016. In addition, LLNL PIs also supported 57 NLUF shots on Omega and 31 NLUF shots on EP, in collaboration with the academic community.

  5. Automated system for handling tritiated mixed waste

    International Nuclear Information System (INIS)

    Dennison, D.K.; Merrill, R.D.; Reitz, T.C.

    1995-03-01

    Lawrence Livermore National Laboratory (LLNL) is developing a semi system for handling, characterizing, processing, sorting, and repackaging hazardous wastes containing tritium. The system combines an IBM-developed gantry robot with a special glove box enclosure designed to protect operators and minimize the potential release of tritium to the atmosphere. All hazardous waste handling and processing will be performed remotely, using the robot in a teleoperational mode for one-of-a-kind functions and in an autonomous mode for repetitive operations. Initially, this system will be used in conjunction with a portable gas system designed to capture any gaseous-phase tritium released into the glove box. This paper presents the objectives of this development program, provides background related to LLNL's robotics and waste handling program, describes the major system components, outlines system operation, and discusses current status and plans

  6. A case-study of landfill minimization and material recovery via waste co-gasification in a new waste management scheme.

    Science.gov (United States)

    Tanigaki, Nobuhiro; Ishida, Yoshihiro; Osada, Morihiro

    2015-03-01

    This study evaluates municipal solid waste co-gasification technology and a new solid waste management scheme, which can minimize final landfill amounts and maximize material recycled from waste. This new scheme is considered for a region where bottom ash and incombustibles are landfilled or not allowed to be recycled due to their toxic heavy metal concentration. Waste is processed with incombustible residues and an incineration bottom ash discharged from existent conventional incinerators, using a gasification and melting technology (the Direct Melting System). The inert materials, contained in municipal solid waste, incombustibles and bottom ash, are recycled as slag and metal in this process as well as energy recovery. Based on this new waste management scheme with a co-gasification system, a case study of municipal solid waste co-gasification was evaluated and compared with other technical solutions, such as conventional incineration, incineration with an ash melting facility under certain boundary conditions. From a technical point of view, co-gasification produced high quality slag with few harmful heavy metals, which was recycled completely without requiring any further post-treatment such as aging. As a consequence, the co-gasification system had an economical advantage over other systems because of its material recovery and minimization of the final landfill amount. Sensitivity analyses of landfill cost, power price and inert materials in waste were also conducted. The higher the landfill costs, the greater the advantage of the co-gasification system has. The co-gasification was beneficial for landfill cost in the range of 80 Euro per ton or more. Higher power prices led to lower operation cost in each case. The inert contents in processed waste had a significant influence on the operating cost. These results indicate that co-gasification of bottom ash and incombustibles with municipal solid waste contributes to minimizing the final landfill amount and has

  7. Feasibility Studies on Pipeline Disposal of Concentrated Copper Tailings Slurry for Waste Minimization

    Science.gov (United States)

    Senapati, Pradipta Kumar; Mishra, Barada Kanta

    2017-06-01

    The conventional lean phase copper tailings slurry disposal systems create pollution all around the disposal area through seepage and flooding of waste slurry water. In order to reduce water consumption and minimize pollution, the pipeline disposal of these waste slurries at high solids concentrations may be considered as a viable option. The paper presents the rheological and pipeline flow characteristics of copper tailings samples in the solids concentration range of 65-72 % by weight. The tailings slurry indicated non-Newtonian behaviour at these solids concentrations and the rheological data were best fitted by Bingham plastic model. The influence of solids concentration on yield stress and plastic viscosity for the copper tailings samples were discussed. Using a high concentration test loop, pipeline experiments were conducted in a 50 mm nominal bore (NB) pipe by varying the pipe flow velocity from 1.5 to 3.5 m/s. A non-Newtonian Bingham plastic pressure drop model predicted the experimental data reasonably well for the concentrated tailings slurry. The pressure drop model was used for higher size pipes and the operating conditions for pipeline disposal of concentrated copper tailings slurry in a 200 mm NB pipe with respect to specific power consumption were discussed.

  8. From waste minimization to ISO 14000: Taiwan`s experience and prospects

    Energy Technology Data Exchange (ETDEWEB)

    Wen-Huei Chen; Wain-Sun Hou [China Technical Consultants, Inc., Taipei (Taiwan, Province of China)

    1996-12-31

    Taiwan has completed a very successful five-year industrial waste minimization (IWM) demonstration and promotion project sponsored by the government. From 1990 to 1995, the project successfully disseminated the IWM concept of pollution prevention (P2) to industries. It effectively reduced industrial waste while significantly benefitting the economy by assisting industries in implementing in-plant IWM programs. In July 1995, the second stage of the five-year IWM and ISO 14000 promotion project was initiated for further promoting the IWM, P2, and cleaner production and, in particular, coping with the upcoming international environmental management standards (ISO 14000). To assist industries in establishing an environmental management system (EMS) and accumulating related experience, an EMS pilot demonstration project of five model industries and an ISO 14001 EMS demonstration and promotion project for 22 factories in 13 industries were initiated in October 1995 and August 1996, respectively. These projects can assist Taiwan`s industries in changing the constitution of their enterprises, enhancing competition in the international market, and helping our nation achieve the forerunner`s profits in sustainable development. 9 refs., 3 figs.

  9. Application of lean six sigma to waste minimization in cigarette paper industry

    Science.gov (United States)

    Syahputri, K.; Sari, R. M.; Anizar; Tarigan, I. R.; Siregar, I.

    2018-02-01

    The cigarette paper industry is one of the industry that is always experiencing increasing demand from consumers. Consumer expectations for the products produced also increased both in terms of quality and quantity. The company continuously improves the quality of its products by trying to minimize nonconformity, waste and improve the efficiency of the whole production process of the company. In this cigarette industry, there is a disability whose value is above the company’s defect tolerance that is 10% of the production amount per month. Another problem also occurs in the production time is too long due to the many activities that are not value added (non value added activities) on the production floor. To overcome this problem, it is necessary to improve the production process of cigarette paper and minimize production time by reducing non value added activities. Repairs done with Lean Six Sigma. Lean Six Sigma is a combination of Lean and Six Sigma concept with DMAIC method (Define, Measure, Analyze, Improve, Control). With this Lean approach, obtained total production time of 1479.13 minutes proposal with cycle efficiency process increased by 12.64%.

  10. Minimization of the volume and Pu content of the waste generated at a plutonium fuel fabrication plant

    International Nuclear Information System (INIS)

    Pauwels, H.

    1992-01-01

    The amounts of waste generated during 1987, 1989 and a past reference period have been reported in great detail. The main conclusions which can be drawn from these figures are: (i) for all kinds of waste, the waste-to-product ratio has decreased very substantially during the past few years. This reduction results partly from a scale effect, i.e. the better load factor of the plant, and partly from Belgonucleare's continuous effort to minimize the radioactive waste arisings; (ii) the ratio of the Pu content of the waste to the total Pu throughput of the plant has also decreased substantially; (iii) the mean Pu content of the solid Pu contaminated waste equals 1.39 g Pu per unit volume of 25 l. Only for a small fraction of this waste (<5% by volume) does the Pu content exceed 5 g per unit volume of 25 l; (iv) even after the implementation of waste reducing measures, some 45% of the solid Pu contaminated waste is generated by operations which involve the handling and transfer of powders. Finally, some 63% of the total amount of Pu in the waste can be imputed to these operations

  11. LLNL NESHAPs 2015 Annual Report - June 2016

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, K. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gallegos, G. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); MacQueen, D. H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wegrecki, A. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-06-01

    Lawrence Livermore National Security, LLC operates facilities at Lawrence Livermore National Laboratory (LLNL) in which radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) National Emission Standards for Hazardous Air Pollutants (NESHAPs) in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H, which regulates radionuclide emissions to air from Department of Energy (DOE) facilities. Specifically, NESHAPs limits the emission of radionuclides to the ambient air to levels resulting in an annual effective dose equivalent of 10 mrem (100 μSv) to any member of the public. Using measured and calculated emissions, and building-specific and common parameters, LLNL personnel applied the EPA-approved computer code, CAP88-PC, Version 4.0.1.17, to calculate the dose to the maximally exposed individual member of the public for the Livermore Site and Site 300.

  12. High intensity positron program at LLNL

    International Nuclear Information System (INIS)

    Asoka-Kumar, P.; Howell, R.; Stoeffl, W.; Carter, D.

    1999-01-01

    Lawrence Livermore National Laboratory (LLNL) is the home of the world's highest current beam of keV positrons. The potential for establishing a national center for materials analysis using positron annihilation techniques around this capability is being actively pursued. The high LLNL beam current will enable investigations in several new areas. We are developing a positron microprobe that will produce a pulsed, focused positron beam for 3-dimensional scans of defect size and concentration with submicron resolution. Below we summarize the important design features of this microprobe. Several experimental end stations will be available that can utilize the high current beam with a time distribution determined by the electron linac pulse structure, quasi-continuous, or bunched at 20 MHz, and can operate in an electrostatic or (and) magnetostatic environment. Some of the planned early experiments are: two-dimensional angular correlation of annihilation radiation of thin films and buried interfaces, positron diffraction holography, positron induced desorption, and positron induced Auger spectroscopy

  13. High intensity positron program at LLNL

    International Nuclear Information System (INIS)

    Asoka-Kumar, P.; Howell, R.H.; Stoeffl, W.

    1998-01-01

    Lawrence Livermore National Laboratory (LLNL) is the home of the world's highest current beam of keV positrons. The potential for establishing a national center for materials analysis using positron annihilation techniques around this capability is being actively pursued. The high LLNL beam current will enable investigations in several new areas. We are developing a positron microprobe that will produce a pulsed, focused positron beam for 3-dimensional scans of defect size and concentration with submicron resolution. Below we summarize the important design features of this microprobe. Several experimental end stations will be available that can utilize the high current beam with a time distribution determined by the electron linac pulse structure, quasi-continuous, or bunched at 20 MHz, and can operate in an electrostatic or (and) magnetostatic environment. Some of the planned early experiments are: two-dimensional angular correlation of annihilation radiation of thin films and buried interfaces, positron diffraction holography, positron induced desorption, and positron induced Auger spectra

  14. LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition

    Energy Technology Data Exchange (ETDEWEB)

    Bronson, M.C.

    1997-10-01

    The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium.

  15. LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition

    International Nuclear Information System (INIS)

    Bronson, M.C.

    1997-01-01

    The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium

  16. LLNL high-field coil program

    International Nuclear Information System (INIS)

    Miller, J.R.

    1986-01-01

    An overview is presented of the LLNL High-Field Superconducting Magnet Development Program wherein the technology is being developed for producing fields in the range of 15 T and higher for both mirror and tokamak applications. Applications requiring less field will also benefit from this program. In addition, recent results on the thermomechanical performance of cable-in-conduit conductor systems are presented and their importance to high-field coil design discussed

  17. LIFTERS-hyperspectral imaging at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Fields, D. [Lawrence Livermore National Lab., CA (United States); Bennett, C.; Carter, M.

    1994-11-15

    LIFTIRS, the Livermore Imaging Fourier Transform InfraRed Spectrometer, recently developed at LLNL, is an instrument which enables extremely efficient collection and analysis of hyperspectral imaging data. LIFTIRS produces a spatial format of 128x128 pixels, with spectral resolution arbitrarily variable up to a maximum of 0.25 inverse centimeters. Time resolution and spectral resolution can be traded off for each other with great flexibility. We will discuss recent measurements made with this instrument, and present typical images and spectra.

  18. Probabilistic Seismic Hazards Update for LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Menchawi, O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fernandez, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-03-30

    Fugro Consultants, Inc. (FCL) completed the Probabilistic Seismic Hazard Analysis (PSHA) performed for Building 332 at the Lawrence Livermore National Laboratory (LLNL), near Livermore, CA. The study performed for the LLNL site includes a comprehensive review of recent information relevant to the LLNL regional tectonic setting and regional seismic sources in the vicinity of the site and development of seismic wave transmission characteristics. The Seismic Source Characterization (SSC), documented in Project Report No. 2259-PR-02 (FCL, 2015b), and Ground Motion Characterization (GMC), documented in Project Report No. 2259-PR-06 (FCL, 2015a) were developed in accordance with ANS/ANSI 2.29- 2008 Level 2 PSHA guidelines. The ANS/ANSI 2.29-2008 Level 2 PSHA framework is documented in Project Report No. 2259-PR-05 (FCL, 2016a). The Hazard Input Document (HID) for input into the PSHA developed from the SSC and GMC is presented in Project Report No. 2259-PR-04 (FCL, 2016b). The site characterization used as input for development of the idealized site profiles including epistemic uncertainty and aleatory variability is presented in Project Report No. 2259-PR-03 (FCL, 2015c). The PSHA results are documented in Project Report No. 2259-PR-07 (FCL, 2016c).

  19. Lessons Learned at Envirocare of Utah's Containerized Waste Facility (CWF): Dose Minimization Through ALARA Techniques and Tools

    International Nuclear Information System (INIS)

    Heckman, J.; Gardner, J.; Ledoux, M. R.

    2003-01-01

    Envirocare of Utah, Inc. (Envirocare) commenced operation of its Class A Containerized Waste Facility (CWF) on October 25, 2001. The opening of this facility began a new era for Envirocare, in that; their core business had always been low level, high volume, bulk radioactive waste. The CWF commenced operations to dispose of low level, low volume, high activity, containerized radioactive waste. Due to the potential for high dose rates on the waste disposal containers, the ALARA principle (As Low As Reasonably Achievable) plays an important role in the operation of the CWF and its mission to properly dispose of waste while minimizing doses to the workers, public, and the environment. This paper will enumerate some of the efforts made by the management and staff of the CWF that have contributed to significant dose reductions

  20. Chelation technology: a promising green approach for resource management and waste minimization.

    Science.gov (United States)

    Chauhan, Garima; Pant, K K; Nigam, K D P

    2015-01-01

    Green chemical engineering recognises the concept of developing innovative environmentally benign technologies to protect human health and ecosystems. In order to explore this concept for minimizing industrial waste and for reducing the environmental impact of hazardous chemicals, new greener approaches need to be adopted for the extraction of heavy metals from industrial waste. In this review, a range of conventional processes and new green approaches employed for metal extraction are discussed in brief. Chelation technology, a modern research trend, has shown its potential to develop sustainable technology for metal extraction from various metal-contaminated sites. However, the interaction mechanism of ligands with metals and the ecotoxicological risk associated with the increased bioavailability of heavy metals due to the formation of metal-chelant complexes is still not sufficiently explicated in the literature. Therefore, a need was felt to provide a comprehensive state-of-the-art review of all aspects associated with chelation technology to promote this process as a green chemical engineering approach. This article elucidates the mechanism and thermodynamics associated with metal-ligand complexation in order to have a better understanding of the metal extraction process. The effects of various process parameters on the formation and stability of complexes have been elaborately discussed with respect to optimizing the chelation efficiency. The non-biodegradable attribute of ligands is another important aspect which is currently of concern. Therefore, biotechnological approaches and computational tools have been assessed in this review to illustrate the possibility of ligand degradation, which will help the readers to look for new environmentally safe mobilizing agents. In addition, emerging trends and opportunities in the field of chelation technology have been summarized and the diverse applicability of chelation technology in metal extraction from

  1. Waste minimization through process optimization/integration and resource management at eco-friendly Heavy Water Plants

    International Nuclear Information System (INIS)

    Nageshri, Jagdish; Gupta, S.K.

    2004-01-01

    Heavy Water Board has celebrated 2003 as Environmental Conservation Year captivating a range of enviro-friendly measures. This article attempts to give a brief overview of the outcome of systems and adapted procedures for waste minimization through process integration and resource management at Heavy Water Plants

  2. The use of absorption spectroscopy of plutonium to minimize waste streams

    International Nuclear Information System (INIS)

    Vaughn, R.B.; Berg, J.; Cisneros, M.

    1997-01-01

    Through the use of absorption spectroscopy we are better able to understand the chemical reactions of plutonium and other actinide elements in solution. In many cases such an understanding can minimize the generation of waste streams by suggesting more optimal chemical conditions for separating these radioactive elements from their host matrix. Many processes are developed using an empirical approach with little understanding of what is actually taking place. One such example is the anion exchange process for Plutonium purification. Various resins have been tested in various solutions and workable outcomes have been produced. However, absorption spectroscopy provides an understanding of why ion exchange works and can determine which compounds complex best with actinides in order to obtain a more efficient and effective separations process. This presentation will touch on the chemistry involved, the spectroscopic instrumentation, and the environmental impacts. Primarily the talk will focus on the chemical technicians involvement in the day to day research, the obstacles encountered, and the environment in which this research was conducted

  3. A case-study of landfill minimization and material recovery via waste co-gasification in a new waste management scheme

    Energy Technology Data Exchange (ETDEWEB)

    Tanigaki, Nobuhiro, E-mail: tanigaki.nobuhiro@eng.nssmc.com [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., (EUROPEAN OFFICE), Am Seestern 8, 40547 Dusseldorf (Germany); Ishida, Yoshihiro [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., 46-59, Nakabaru, Tobata-ku, Kitakyushu, Fukuoka 804-8505 (Japan); Osada, Morihiro [NIPPON STEEL & SUMIKIN ENGINEERING CO., LTD., (Head Office), Osaki Center Building 1-5-1, Osaki, Shinagawa-ku, Tokyo 141-8604 (Japan)

    2015-03-15

    Highlights: • A new waste management scheme and the effects of co-gasification of MSW were assessed. • A co-gasification system was compared with other conventional systems. • The co-gasification system can produce slag and metal with high-quality. • The co-gasification system showed an economic advantage when bottom ash is landfilled. • The sensitive analyses indicate an economic advantage when the landfill cost is high. - Abstract: This study evaluates municipal solid waste co-gasification technology and a new solid waste management scheme, which can minimize final landfill amounts and maximize material recycled from waste. This new scheme is considered for a region where bottom ash and incombustibles are landfilled or not allowed to be recycled due to their toxic heavy metal concentration. Waste is processed with incombustible residues and an incineration bottom ash discharged from existent conventional incinerators, using a gasification and melting technology (the Direct Melting System). The inert materials, contained in municipal solid waste, incombustibles and bottom ash, are recycled as slag and metal in this process as well as energy recovery. Based on this new waste management scheme with a co-gasification system, a case study of municipal solid waste co-gasification was evaluated and compared with other technical solutions, such as conventional incineration, incineration with an ash melting facility under certain boundary conditions. From a technical point of view, co-gasification produced high quality slag with few harmful heavy metals, which was recycled completely without requiring any further post-treatment such as aging. As a consequence, the co-gasification system had an economical advantage over other systems because of its material recovery and minimization of the final landfill amount. Sensitivity analyses of landfill cost, power price and inert materials in waste were also conducted. The higher the landfill costs, the greater the

  4. The development of control technologies applied to waste processing operations

    International Nuclear Information System (INIS)

    Grasz, E.; Baker, S.; Couture, S.; Dennison, D.; Holliday, M.; Hurd, R.; Kettering, B.; Merrill, R.; Wilhelmson, K.

    1993-02-01

    Typical waste and residue processes involve some level of human interaction. The risk of exposure to unknown hazardous materials and the potential for radiation contamination provide the impetus for physically separating or removing operators from such processing steps. Technologies that facilitate separation of the operator from potential contamination include glove box robotics; modular systems for remote and automated servicing; and interactive controls that minimize human intervention. Lawrence Livermore National Laboratory (LLNL) is developing an automated system which by design will supplant the operator for glove box tasks, thus affording protection from the risk of radiation exposure and minimizing operator associated waste.This paper describes recent accomplishments in technology development and integration, and outlines the future goals at LLNL for achieving this integrated, interactive control capability

  5. LLNL/JNC repository collaboration interim progress report

    International Nuclear Information System (INIS)

    Bourcier, W.L.; Couch, R.G.; Gansemer, J.; Halsey, W.G.; Palmer, C.E.; Sinz, K.H.; Stout, R.B.; Wijesinghe, A.; Wolery, T.J.

    1999-01-01

    Under this Annex, a research program on the near-field performance assessment related to the geological disposal of radioactive waste will be carried out at the Lawrence Livermore National Laboratory (LLNL) in close collaboration with the Power Reactor and Nuclear Fuel Development Corporation of Japan (PNC). This program will focus on activities that provide direct support for PNC's near-term and long-term needs that will, in turn, utilize and further strengthen US capabilities for radioactive waste management. The work scope for two years will be designed based on the PNC's priorities for its second progress report (the H12 report) of research and development for high-level radioactive waste disposal and on the interest and capabilities of the LLNL. The work will focus on the chemical modeling for the near-field environment and long-term mechanical modeling of engineered barrier system as it evolves. Certain activities in this program will provide for a final iteration of analyses to provide additional technical basis prior to the year 2000 as determined in discussions with the PNC's technical coordinator. The work for two years will include the following activities: Activity 1: Chemical Modeling of EBS Materials Interactions--Task 1.1 Chemical Modeling of Iron Effects on Borosilicate Glass Durability; and Task 1.2 Changes in Overpack and Bentonite Properties Due to Metal, Bentonite and Water Interactions. Activity 2: Thermodynamic Database Validation and Comparison--Task 2.1 Set up EQ3/6 to Run with the Pitzer-based PNC Thermodynamic Data Base; Task 2.2 Provide Expert Consultation on the Thermodynamic Data Base; and Task 2.3 Provide Analysis of Likely Solubility Controls on Selenium. Activity 3: Engineered Barrier Performance Assessment of the Unsaturated, Oxidizing Transient--Task 3.1 Apply YMIM to PNC Transient EBS Performance; Task 3.2 Demonstrate Methods for Modeling the Return to Reducing Conditions; and Task 3.3 Evaluate the Potential for Stress Corrosion

  6. Application of glove box robotics to hazardous waste management

    International Nuclear Information System (INIS)

    Dennison, D.K.; Hurd, R.L.; Merrill, R.D.; Reitz, T.C.

    1995-02-01

    Lawrence Livermore Laboratory (LLNL) is developing a semi-automated system for handling, characterizing, processing, sorting, and repackaging hazardous wastes containing tritium. The system combines an IBM developed gantry robot with a special glove box enclosure designed to protect the operators and minimize the potential release of tritium to the atmosphere. All hazardous waste handling and processing will be performed remotely using the robot in a telerobotic mode for one-of-a-kind functions and in an autonomous mode for repetitive type operations. The system will initially be used in conjunction with a portable gas system designed to capture any gaseous phase tritium released into the glove box. This paper presents the objectives of this program, provides background related to LLNL's robotics and waste handling program, describes the major system components, outlines system operation, and discusses current status and plans

  7. Summary of Environmental Data Analysis and Work Performed by Lawrence Livermore National Laboratory (LLNL) in Support of the Navajo Nation Abandoned Mine Lands Project at Tse Tah, Arizona

    Energy Technology Data Exchange (ETDEWEB)

    Taffet, Michael J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Esser, Bradley K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Madrid, Victor M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-05-17

    This report summarizes work performed by Lawrence Livermore National Laboratory (LLNL) under Navajo Nation Services Contract CO9729 in support of the Navajo Abandoned Mine Lands Reclamation Program (NAMLRP). Due to restrictions on access to uranium mine waste sites at Tse Tah, Arizona that developed during the term of the contract, not all of the work scope could be performed. LLNL was able to interpret environmental monitoring data provided by NAMLRP. Summaries of these data evaluation activities are provided in this report. Additionally, during the contract period, LLNL provided technical guidance, instructional meetings, and review of relevant work performed by NAMLRP and its contractors that was not contained in the contract work scope.

  8. The LLNL portable tritium processing system

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The end of the Cold War significantly reduced the need for facilities to handle radioactive materials for the US nuclear weapons program. The LLNL Tritium Facility was among those slated for decommissioning. The plans for the facility have since been reversed, and it remains open. Nevertheless, in the early 1990s, the cleanup (the Tritium Inventory Removal Project) was undertaken. However, removing the inventory of tritium within the facility and cleaning up any pockets of high-level residual contamination required that we design a system adequate to the task and meeting today's stringent standards of worker and environmental protection. In collaboration with Sandia National Laboratory and EG ampersand G Mound Applied Technologies, we fabricated a three-module Portable Tritium Processing System (PTPS) that meets current glovebox standards, is operated from a portable console, and is movable from laboratory to laboratory for performing the basic tritium processing operations: pumping and gas transfer, gas analysis, and gas-phase tritium scrubbing. The Tritium Inventory Removal Project is now in its final year, and the portable system continues to be the workhorse. To meet a strong demand for tritium services, the LLNL Tritium Facility will be reconfigured to provide state-of-the-art tritium and radioactive decontamination research and development. The PTPS will play a key role in this new facility

  9. LLNL Livermore site Groundwater Surveillance Plan

    International Nuclear Information System (INIS)

    1992-04-01

    Department of Energy (DOE) Order 5400.1 establishes environ-mental protection program requirements, authorities, and responsibilities for DOE operations to assume compliance with federal, state, and local environmental protection laws and regulations; Federal Executive Orders; and internal DOE policies. ne DOE Order contains requirements and guidance for environmental monitoring programs, the objectives of which are to demonstrate compliance with legal and regulatory requirements imposed by federal, state, and local agencies; confirm adherence to DOE environmental protection polices; and support environmental management decisions. The environmental monitoring programs consist of two major activities: (1) measurement and monitoring of effluents from DOE operations, and (2) surveillance through measurement, monitoring, and calculation of the effects of those operations on the environment and public health. The latter concern, that of assessing the effects, if any, of Lawrence Livermore National Laboratory (LLNL) operations and activities on on-site and off-site surface waters and groundwaters is addressed by an Environmental Surveillance Program being developed by LLNL. The Groundwater Surveillance Plan presented here has been developed on a sitespecific basis, taking into consideration facility characteristics, applicable regulations, hazard potential, quantities and concentrations of materials released, the extent and use of local water resources, and specific local public interest and concerns

  10. High intensity positron program at LLNL

    International Nuclear Information System (INIS)

    Asoka-Kumar, P.; Howell, R.; Stoeffl, W.; Carter, D.

    1999-01-01

    Lawrence Livermore National Laboratory (LLNL) is the home of the world close-quote s highest current beam of keV positrons. The potential for establishing a national center for materials analysis using positron annihilation techniques around this capability is being actively pursued. The high LLNL beam current will enable investigations in several new areas. We are developing a positron microprobe that will produce a pulsed, focused positron beam for 3-dimensional scans of defect size and concentration with submicron resolution. Below we summarize the important design features of this microprobe. Several experimental end stations will be available that can utilize the high current beam with a time distribution determined by the electron linac pulse structure, quasi-continuous, or bunched at 20 MHz, and can operate in an electrostatic or (and) magnetostatic environment. Some of the planned early experiments are: two-dimensional angular correlation of annihilation radiation of thin films and buried interfaces, positron diffraction holography, positron induced desorption, and positron induced Auger spectroscopy. copyright 1999 American Institute of Physics

  11. Development and characterization of new high-level waste form containing LiCl KCl eutectic salts for achieving waste minimization from pyroprocessing

    International Nuclear Information System (INIS)

    Cho, Yong Zun; Kim, In Tae; Park, Hwan Seo; Ahn, Byeung Gil; Eun, Hee Chul; Son, Seock Mo; Ah, Su Na

    2011-12-01

    The purpose of this project is to develop new high level waste (HLW) forms and fabrication processes to dispose of active metal fission products that are removed from electrorefiner salts in the pyroprocessing based fuel cycle. The current technology for disposing of active metal fission products in pyroprocessing involves non selectively discarding of fission product loaded salt in a glass-bonded sodalite ceramic waste form. Selective removal of fission products from the molten salt would greatly minimize the amount of HLW generated and methods were developed to achieve selective separation of fission products during a previous I NERI research project (I NERI 2006 002 K). This I NERI project proceeds from the previous project with the development of suitable waste forms to immobilize the separated fission products. The Korea Atomic Energy Research Institute (KAERI) has focused primarily on developing these waste forms using surrogate waste materials, while the Idaho National Laboratory (INL) has demonstrated fabrication of these waste forms using radioactive electrorefiner salts in hot cell facilities available at INL. Testing and characterization of these radioactive materials was also performed to determine the physical, chemical, and durability properties of the waste forms

  12. Analysis of the application of decontamination technologies to radioactive metal waste minimization using expert systems

    Energy Technology Data Exchange (ETDEWEB)

    Bayrakal, Suna [Iowa State Univ., Ames, IA (United States)

    1993-09-30

    Radioactive metal waste makes up a significant portion of the waste currently being sent for disposal. Recovery of this metal as a valuable resource is possible through the use of decontamination technologies. Through the development and use of expert systems a comparison can be made of laser decontamination, a technology currently under development at Ames Laboratory, with currently available decontamination technologies for applicability to the types of metal waste being generated and the effectiveness of these versus simply disposing of the waste. These technologies can be technically and economically evaluated by the use of expert systems techniques to provide a waste management decision making tool that generates, given an identified metal waste, waste management recommendations. The user enters waste characteristic information as input and the system then recommends decontamination technologies, determines residual contamination levels and possible waste management strategies, carries out a cost analysis and then ranks, according to cost, the possibilities for management of the waste. The expert system was developed using information from literature and personnel experienced in the use of decontamination technologies and requires validation by human experts and assignment of confidence factors to the knowledge represented within.

  13. Analysis of the application of decontamination technologies to radioactive metal waste minimization using expert systems

    International Nuclear Information System (INIS)

    Bayrakal, S.

    1993-01-01

    Radioactive metal waste makes up a significant portion of the waste currently being sent for disposal. Recovery of this metal as a valuable resource is possible through the use of decontamination technologies. Through the development and use of expert systems a comparison can be made of laser decontamination, a technology currently under development at Ames Laboratory, with currently available decontamination technologies for applicability to the types of metal waste being generated and the effectiveness of these versus simply disposing of the waste. These technologies can be technically and economically evaluated by the use of expert systems techniques to provide a waste management decision making tool that generates, given an identified metal waste, waste management recommendations. The user enters waste characteristic information as input and the system then recommends decontamination technologies, determines residual contamination levels and possible waste management strategies, carries out a cost analysis and then ranks, according to cost, the possibilities for management of the waste. The expert system was developed using information from literature and personnel experienced in the use of decontamination technologies and requires validation by human experts and assignment of confidence factors to the knowledge represented within

  14. Waste minimization and pollution prevention in D ampersand D operations at the Argonne National Laboratory-East site

    International Nuclear Information System (INIS)

    Boing, L.E.; Coffey, M.J.; Ditch, R.W.; Fellhauer, C.R.; Rose, R.W.

    1996-01-01

    Argonne National Laboratory (ANL) is implementing waste minimization and pollution prevention activities into its conduct of decontamination and decommissioning (D ampersand D) projects. Many of these activities are rather straight forward and simple approaches, yet they are often overlooked and not implemented as often as they should or could be. Specific activities involving recycling and reuse of materials and structures, which have proven useful in lowering decommissioning and disposal costs on D ampersand D projects at ANL are presented

  15. Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

    International Nuclear Information System (INIS)

    Kyrs, M.; Moravec, A.

    1988-06-01

    The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

  16. Proposed LLNL electron beam ion trap

    International Nuclear Information System (INIS)

    Marrs, R.E.; Egan, P.O.; Proctor, I.; Levine, M.A.; Hansen, L.; Kajiyama, Y.; Wolgast, R.

    1985-01-01

    The interaction of energetic electrons with highly charged ions is of great importance to several research fields such as astrophysics, laser fusion and magnetic fusion. In spite of this importance there are almost no measurements of electron interaction cross sections for ions more than a few times ionized. To address this problem an electron beam ion trap (EBIT) is being developed at LLNL. The device is essentially an EBIS except that it is not intended as a source of extracted ions. Instead the (variable energy) electron beam interacting with the confined ions will be used to obtain measurements of ionization cross sections, dielectronic recombination cross sections, radiative recombination cross sections, energy levels and oscillator strengths. Charge-exchange recombinaion cross sections with neutral gasses could also be measured. The goal is to produce and study elements in many different charge states up to He-like xenon and Ne-like uranium. 5 refs., 2 figs

  17. FY14 LLNL OMEGA Experimental Programs

    Energy Technology Data Exchange (ETDEWEB)

    Heeter, R. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fournier, K. B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Baker, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Barrios, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bernstein, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Brown, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Celliers, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chen, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Coppari, F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fratanduono, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Johnson, M. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Huntington, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jenei, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kraus, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ma, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Martinez, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McNabb, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Millot, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Moore, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Nagel, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Park, H. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Patel, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Perez, F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ping, Y. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pollock, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ross, J. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rygg, J. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Zylstra, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Collins, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Landen, O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wan, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hsing, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-10-13

    In FY14, LLNL’s High-Energy-Density Physics (HED) and Indirect Drive Inertial Confinement Fusion (ICF-ID) programs conducted several campaigns on the OMEGA laser system and on the EP laser system, as well as campaigns that used the OMEGA and EP beams jointly. Overall these LLNL programs led 324 target shots in FY14, with 246 shots using just the OMEGA laser system, 62 shots using just the EP laser system, and 16 Joint shots using Omega and EP together. Approximately 31% of the total number of shots (62 OMEGA shots, 42 EP shots) shots supported the Indirect Drive Inertial Confinement Fusion Campaign (ICF-ID). The remaining 69% (200 OMEGA shots and 36 EP shots, including the 16 Joint shots) were dedicated to experiments for High- Energy-Density Physics (HED). Highlights of the various HED and ICF campaigns are summarized in the following reports.

  18. FY15 LLNL OMEGA Experimental Programs

    Energy Technology Data Exchange (ETDEWEB)

    Heeter, R. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Baker, K. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Barrios, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beckwith, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Casey, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Celliers, P. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chen, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Coppari, F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fournier, K. B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fratanduono, D. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Frenje, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Huntington, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kraus, R. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lazicki, A. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Martinez, D. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McNaney, J. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Millot, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pak, A. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Park, H. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ping, Y. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pollock, B. B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Smith, R. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wehrenberg, C. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Widmann, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Collins, G. W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Landen, O. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wan, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hsing, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-12-04

    In FY15, LLNL’s High-Energy-Density Physics (HED) and Indirect Drive Inertial Confinement Fusion (ICF-ID) programs conducted several campaigns on the OMEGA laser system and on the EP laser system, as well as campaigns that used the OMEGA and EP beams jointly. Overall these LLNL programs led 468 target shots in FY15, with 315 shots using just the OMEGA laser system, 145 shots using just the EP laser system, and 8 Joint shots using Omega and EP together. Approximately 25% of the total number of shots (56 OMEGA shots and 67 EP shots, including the 8 Joint shots) supported the Indirect Drive Inertial Confinement Fusion Campaign (ICF-ID). The remaining 75% (267 OMEGA shots and 86 EP shots) were dedicated to experiments for High-Energy-Density Physics (HED). Highlights of the various HED and ICF campaigns are summarized in the following reports.

  19. Wastes Management Can Minimize CH4 and N2O Emissions from Wetlands in Indonesia

    Directory of Open Access Journals (Sweden)

    Abdul Hadi

    2015-07-01

    Full Text Available Paddy (Oriza sativa L. and Oil palm (Elaeis guineensis Jack are two important crops and are potential to produce wastes which may lead to huge greenhouse gas emissions if they are not managed properly.  Open burning and conventional composting are commonly practiced by farmers and/or planters to managed agricultural wastes in Indonesia.  A series of research has been carried out  to elucidate (1 the reductions of CH4 and N2O due to incertion of a catalitic converter on burning kiln, (2 the best composting technique of oil palm field wastes, and (3 the effects of oil palm field wastes compost application in oil palm fields and of paddy field wastes biochar in integrated oil palm-paddy fields.  The results showed that CH4 and N2O emissions from paddy field wastes (i.e., rice straw or rice husk was lower than that from oil palm empty fruit bunch (EFB.  Furthermore, insertion of a catalytic converter into pyrolysis installation reduced the CO2, CH4 and N2O emissions from paddy field wastes as much as 14.5, 17.8 and 11.1%, respectively.  Incorporation of EFB compost did not increase greenhouse gas emission from oil palm fields. These results suggest that biochar and EFB compost can be practiced to manage agricultural wastes in Indonesia.

  20. Application of molten salt oxidation for the minimization and recovery of plutonium-238 contaminated wastes

    International Nuclear Information System (INIS)

    Wishau, R.; Ramsey, K.B.; Montoya, A.

    1998-01-01

    This paper presents the technical and economic feasibility of molten salt oxidation technology as a volume reduction and recovery process for 238 Pu contaminated waste. Combustible low-level waste material contaminated with 238 Pu residue is destroyed by oxidation in a 900 C molten salt reaction vessel. The combustible waste is destroyed creating carbon dioxide and steam and a small amount of ash and insoluble 2328 Pu in the spent salt. The valuable 238 Pu is recycled using aqueous recovery techniques. Experimental test results for this technology indicate a plutonium recovery efficiency of 99%. Molten salt oxidation stabilizes the waste converting it to a non-combustible waste. Thus installation and use of molten salt oxidation technology will substantially reduce the volume of 238 Pu contaminated waste. Cost-effectiveness evaluations of molten salt oxidation indicate a significant cost savings when compared to the present plans to package, or re-package, certify and transport these wastes to the Waste Isolation Pilot Plant for permanent disposal. Clear and distinct cost advantages exist for MSO when the monetary value of the recovered 238 Pu is considered

  1. 1997 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    Segall, P.

    1998-01-01

    Hanford's missions are to safely clean up and manage the site's legacy wastes, and to develop and deploy science and technology. Through these missions Hanford will contribute to economic diversification of the region. Hanford's environmental management or cleanup mission is to protect the health and safety of the public, workers, and the environment; control hazardous materials; and utilize the assets (people, infra structure, site) for other missions. Hanford's science and technology mission is to develop and deploy science and technology in the service of the nation including stewardship of the Hanford Site. Pollution Prevention is a key to the success of these missions by reducing the amount of waste to be managed and identifying/implementing cost effective waste reduction projects. Hanford's original mission, the production of nuclear materials for the nation's defense programs, lasted more than 40 years, and like most manufacturing operations, Hanford's operations generated large quantities of waste and pollution. However, the by-products from Hanford operations pose unique problems like radiation hazards, vast volumes of contaminated water and soil, and many contaminated structures including reactors, chemical plants and evaporation ponds. The cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single shell storage tanks, treating 28 double shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored on site, removing numerous structures, and dealing with significant solid waste, ground water, and land restoration issues

  2. Application of molten salt oxidation for the minimization and recovery of plutonium-238 contaminated wastes

    Energy Technology Data Exchange (ETDEWEB)

    Wishau, R.

    1998-05-01

    Molten salt oxidation (MSO) is proposed as a {sup 238}Pu waste treatment technology that should be developed for volume reduction and recovery of {sup 238}Pu and as an alternative to the transport and permanent disposal of {sup 238}Pu waste to the WIPP repository. In MSO technology, molten sodium carbonate salt at 800--900 C in a reaction vessel acts as a reaction media for wastes. The waste material is destroyed when injected into the molten salt, creating harmless carbon dioxide and steam and a small amount of ash in the spent salt. The spent salt can be treated using aqueous separation methods to reuse the salt and to recover 99.9% of the precious {sup 238}Pu that was in the waste. Tests of MSO technology have shown that the volume of combustible TRU waste can be reduced by a factor of at least twenty. Using this factor the present inventory of 574 TRU drums of {sup 238}Pu contaminated wastes is reduced to 30 drums. Further {sup 238}Pu waste costs of $22 million are avoided from not having to repackage 312 of the 574 drums to a drum total of more than 4,600 drums. MSO combined with aqueous processing of salts will recover approximately 1.7 kilograms of precious {sup 238}Pu valued at 4 million dollars (at $2,500/gram). Thus, installation and use of MSO technology at LANL will result in significant cost savings compared to present plans to transport and dispose {sup 238}Pu TRU waste to the WIPP site. Using a total net present value cost for the MSO project as $4.09 million over a five-year lifetime, the project can pay for itself after either recovery of 1.6 kg of Pu or through volume reduction of 818 drums or a combination of the two. These savings show a positive return on investment.

  3. Application of molten salt oxidation for the minimization and recovery of plutonium-238 contaminated wastes

    International Nuclear Information System (INIS)

    Wishau, R.

    1998-05-01

    Molten salt oxidation (MSO) is proposed as a 238 Pu waste treatment technology that should be developed for volume reduction and recovery of 238 Pu and as an alternative to the transport and permanent disposal of 238 Pu waste to the WIPP repository. In MSO technology, molten sodium carbonate salt at 800--900 C in a reaction vessel acts as a reaction media for wastes. The waste material is destroyed when injected into the molten salt, creating harmless carbon dioxide and steam and a small amount of ash in the spent salt. The spent salt can be treated using aqueous separation methods to reuse the salt and to recover 99.9% of the precious 238 Pu that was in the waste. Tests of MSO technology have shown that the volume of combustible TRU waste can be reduced by a factor of at least twenty. Using this factor the present inventory of 574 TRU drums of 238 Pu contaminated wastes is reduced to 30 drums. Further 238 Pu waste costs of $22 million are avoided from not having to repackage 312 of the 574 drums to a drum total of more than 4,600 drums. MSO combined with aqueous processing of salts will recover approximately 1.7 kilograms of precious 238 Pu valued at 4 million dollars (at $2,500/gram). Thus, installation and use of MSO technology at LANL will result in significant cost savings compared to present plans to transport and dispose 238 Pu TRU waste to the WIPP site. Using a total net present value cost for the MSO project as $4.09 million over a five-year lifetime, the project can pay for itself after either recovery of 1.6 kg of Pu or through volume reduction of 818 drums or a combination of the two. These savings show a positive return on investment

  4. Optimising material procurement for construction waste minimization: An exploration of success factors

    OpenAIRE

    Ajayi, SO; Oyedele, LO; Akinade, OO; Bilal, M; Alaka, HA; Owolabi, HA

    2017-01-01

    Although construction waste occurs during the actual construction activities, there is an understanding that it is caused by activities and actions at design, materials procurement and construction stages of project delivery processes. This study investigates the material procurement and logistics measures for mitigating waste generated by construction activities. In a bid to explore the phenomenon from the perspectives of experts from the construction industry, this study used a combination ...

  5. Proceedings of the tenth annual DOE low-level waste management conference: Session 4: Waste treatment minimization

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains eleven papers on various aspects of low-level radioactive waste management. Topics in this volume include: volume reduction plans; incentitives; and cost proposals; acid detoxification and reclamation; decontamination of lead; leach tests; West Valley demonstration project status report; and DOE's regional management strategies. Individual papers were processed separately for the data base

  6. Minimizing risk associated with shallow burial of waste in semiarid ecosystems: Erosion and vegetation dynamics

    International Nuclear Information System (INIS)

    Breshears, D.D.; Martens, S.N.; Nyhan, J.W.; Springer, E.P.; Wilcox, B.P.

    1994-01-01

    Numerous regulations govern the disposal of low-level radioactive and hazardous waste by burial in shallow pits. The overall goal of these regulations is to reduce the risk to humans and components of the ecosystem for 500 to 1 000 years. Erosional loss of the soil profile covering waste and contamination of groundwater by leachate are two pathways that influence human and ecological risks. Screening calculations for a waste site in a pinyon-juniper woodland at Los Alamos National Laboratory predict the entire 2 m cover of a waste site could be lost by erosion in less than 500 years. In contrast, less than 0.001% of the waste would reach groundwater by leachate. Predicted erosion rates depend highly on plant cover. The boundary between ponderosa pine forest and pinyon-juniper woodland has shifted more than 1 km in less than 50 years in the Los Alamos region and additional boundary shifts have been hypothesized in conjunction with global warming. High erosion rates (> 0.2 cm per year) have been measured in these transition zones. In concert, these results suggest that risk associated with erosional loss of the waste site cover may greatly exceed risks associated with groundwater contamination in semiarid ecosystems

  7. Waste minimization activities in Toyota Motor Corporation; Haikibutsu teigen eno torikumi jokyo

    Energy Technology Data Exchange (ETDEWEB)

    Taguchi, S.; Yamamoto, N.; Kurai, H. [Toyota Motor Corp., Aichi (Japan)

    1998-07-01

    Toyota`s waste reduction efforts based on a drive for dealing with the source of waste generation are introduced. For the propulsion of the policy for dealing directly with the origin of waste, it is necessary to convert the existing manufacturing processes that give high priority to product quality and low production cost into environmental impact reduction oriented processes. In particular, conversion of materials into those that are easier to recycle, technology for reducing defective products, technology for the completion of recycling within the process involved, and the simplification of all the processes are mentioned. For the cleaning job in the machining process, a detergent enhanced in oil/water separating capability is developed, and this prolongs doubly the detergent replacement period and decreases the waste liquid to a 1/4 or less of what the conventional method produces. For the handling of foundry sand that is yielded in great quantities, a flow classification system is developed to replace the conventional gravitational classifier, and the reusable coarse-grain sand in the collected dust which occupies approximately 70% of the whole waste is now recovered for reuse. In the vehicle body coating process, a newly-developed robot arm type coating system is developed, which halves the coating waste. 2 refs., 9 figs., 1 tab.

  8. Compilation of LLNL CUP-2 Data

    Energy Technology Data Exchange (ETDEWEB)

    Eppich, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kips, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lindvall, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-07-31

    The CUP-2 uranium ore concentrate (UOC) standard reference material, a powder, was produced at the Blind River uranium refinery of Eldorado Resources Ltd. in Canada in 1986. This material was produced as part of a joint effort by the Canadian Certified Reference Materials Project and the Canadian Uranium Producers Metallurgical Committee to develop a certified reference material for uranium concentration and the concentration of several impurity constituents. This standard was developed to satisfy the requirements of the UOC mining and milling industry, and was characterized with this purpose in mind. To produce CUP-2, approximately 25 kg of UOC derived from the Blind River uranium refinery was blended, homogenized, and assessed for homogeneity by X-ray fluorescence (XRF) analysis. The homogenized material was then packaged into bottles, containing 50 g of material each, and distributed for analysis to laboratories in 1986. The CUP-2 UOC standard was characterized by an interlaboratory analysis program involving eight member laboratories, six commercial laboratories, and three additional volunteer laboratories. Each laboratory provided five replicate results on up to 17 analytes, including total uranium concentration, and moisture content. The selection of analytical technique was left to each participating laboratory. Uranium was reported on an “as-received” basis; all other analytes (besides moisture content) were reported on a “dry-weight” basis. A bottle of 25g of CUP-2 UOC standard as described above was purchased by LLNL and characterized by the LLNL Nuclear Forensics Group. Non-destructive and destructive analytical techniques were applied to the UOC sample. Information obtained from short-term techniques such as photography, gamma spectrometry, and scanning electron microscopy were used to guide the performance of longer-term techniques such as ICP-MS. Some techniques, such as XRF and ICP-MS, provided complementary types of data. The results

  9. Use of plutonium and minor actinides as fuel in high temperature pebble bed reactors for waste minimization

    International Nuclear Information System (INIS)

    Meier, Astrid; Bernnat, Wolfgang; Lohnert, Guenther

    2009-01-01

    Energy production by nuclear fission gives rise to longlived radionuclides, such as plutonium and americium. The ''PuMA'' (Plutonium and Minor Actinides Waste Management) research project within the 6th Framework Program of the European Union serves to minimize waste arisings and transmute plutonium and minor actinides from spent LWR fuel elements by means of modular high-temperature reactors (HTR). Coating the fuel, which consists of kernels approx. 250 μm in radius and surrounded by graphite as the moderator material, allows very high operating and accident temperatures and very high burnups. One point examined is whether the inherent safety characteristics known for uranium oxide also exist for (PuO 2 + MAO 2 ) fuel. On the basis of a reference reactor similar to the South African PBMR-400, various loading strategies at maximum burnup are considered with a view to the inherent safety of the HTR. (orig.)

  10. The new LLNL AMS sample changer

    International Nuclear Information System (INIS)

    Roberts, M.L.; Norman, P.J.; Garibaldi, J.L.; Hornady, R.S.

    1993-01-01

    The Center for Accelerator Mass Spectrometry at LLNL has installed a new 64 position AMS sample changer on our spectrometer. This new sample changer has the capability of being controlled manually by an operator or automatically by the AMS data acquisition computer. Automatic control of the sample changer by the data acquisition system is a necessary step towards unattended AMS operation in our laboratory. The sample changer uses a fiber optic shaft encoder for rough rotational indexing of the sample wheel and a series of sequenced pneumatic cylinders for final mechanical indexing of the wheel and insertion and retraction of samples. Transit time from sample to sample varies from 4 s to 19 s, depending on distance moved. Final sample location can be set to within 50 microns on the x and y axis and within 100 microns in the z axis. Changing sample wheels on the new sample changer is also easier and faster than was possible on our previous sample changer and does not require the use of any tools

  11. Contingency plan for the Lawrence Livermore National Laboratory, Site 300, hazardous waste operations

    International Nuclear Information System (INIS)

    Gonzalez, M.A.

    1983-01-01

    This contingency plan for hazardous waste release provides guidance for coordinating response efforts. With a goal to minimize hazards to human health and life; and protect livestock, wildlife, the environment, and property in the event of a fire, explosion, or any unplanned release of hazardous substances or mixtures to the air, water, or soil. In this document, hazardous waste includes all waste substances or mixtures that: contain any of the hazardous substances listed in the Resource Conservation and Recovery Act; have the characteristic of being toxic, flammable, reactive, corrosive, an irritant, and/or a strong sensitizer; are radioactive and are used in experiments at Site 300; or could have a significant effect on the environment. This Plan includes an overview of emergency response capabilities; and responsibilities assigned to both LLNL and non-LLNL emergency response personel

  12. Maintenance of shutdown system in the reactor core to minimize the radioactive waste generation

    International Nuclear Information System (INIS)

    Ponzoni Filho, P.; Fernandes, V.B.

    1988-01-01

    This paper recommends a modification on the actual strategy of going from Cold-Shutdown to Critical, that will save about 6000 liter of boric acid and 30,000 liters of demineralized water for each reactor criticalization. This strategy will reduce the radioactive waste disposal volume to only about 5% of what would be generated following the actual strategy. (author) [pt

  13. Minimization of actinide waste by multi-recycling of thoriated fuels in the EPR reactor

    Directory of Open Access Journals (Sweden)

    Nuttin A.

    2012-02-01

    Full Text Available The multi-recycling of innovative uranium/thorium oxide fuels for use in the European Pressurized water Reactor (EPR has been investigated. If increasing quantities of 238U, the fertile isotope in standard UO2 fuel, are replaced by 232Th, then a greater yield of new fissile material (233U is produced during the cycle than would otherwise be the case. This leads to economies of natural uranium of around 45% if the uranium in the spent fuel is multi-recycled. In addition we show that minor actinide and plutonium waste inventories are reduced and hence waste radio-toxicities and decay heats are up to a factor of 20 lower after 103 years. Two innovative fuel types named S90 and S20, ThO2 mixed with 90% and 20% enriched UO2 respectively, are compared as an alternative to standard uranium oxide (UOX and uranium/plutonium mixed oxide (MOX fuels at the longest EPR fuel discharge burn-ups of 65 GWd/t. Fissile and waste inventories are examined, waste radio-toxicities and decay heats are extracted and safety feedback coefficients are calculated.

  14. Status and direction of waste minimization in the chemical and petrochemical industries

    Energy Technology Data Exchange (ETDEWEB)

    Englande Junior, A.J. [Tulane Univ., New Orleans, LA (United States). School of Public Health and Tropical Medicine

    1993-12-31

    This paper presents an evaluation of the status and direction of toxic/hazardous waste reduction in chemical and petrochemical industries from an international perspective. In almost all cases studied savings have resulted. The importance of pollution prevention by `clean technologies` instead of remediation is stressed. 6 refs., 4 tabs.

  15. Status and direction of waste minimization in the chemical and petrochemical industries

    Energy Technology Data Exchange (ETDEWEB)

    Englande, Junior, A J [Tulane Univ., New Orleans, LA (United States). School of Public Health and Tropical Medicine

    1994-12-31

    This paper presents an evaluation of the status and direction of toxic/hazardous waste reduction in chemical and petrochemical industries from an international perspective. In almost all cases studied savings have resulted. The importance of pollution prevention by `clean technologies` instead of remediation is stressed. 6 refs., 4 tabs.

  16. Waste minimization methods for treating analytical instrumentation effluents at the source

    International Nuclear Information System (INIS)

    Ritter, J.A.; Barnhart, C.

    1995-01-01

    The primary goal of this project was to reduce the amount of hazardous waste being generated by the Savannah River Siste Defense Waste Processing Technology-analytical Laboratory (DWPT-AL). A detailed characterization study was performed on 12 of the liquid effluent streams generated within the DWPT-AL. Two of the streams were not hazardous, and are now being collected separately from the 10 hazardous streams. A secondary goal of the project was to develop in-line methods using primarily adsorption/ion exchange columns to treat liquid effluent as it emerges from the analytical instrument as a slow, dripping flow. Samples from the 10 hazardous streams were treated by adsorption in an experimental apparatus that resembled an in-line or at source column apparatus. The layered adsorbent bed contained activated carbon and ion exchange resin. The column technique did not work on the first three samples of the spectroscopy waste stream, but worked well on the next three samples which were treated in a different column. It was determined that an unusual form of mercury was present in the first three samples. Similarly, two samples of a combined waste stream were rendered nonhazardous, but the last two samples contained acetylnitrile that prevented analysis. The characteristics of these streams changed from the initial characterization study; therefore, continual, in-deptch stream characterization is the key to making this project successful

  17. Waste minimization through high-pressure microwave digestion of soils for gross α/β analyses

    International Nuclear Information System (INIS)

    Yaeger, J.S.; Smith, L.L.

    1995-04-01

    As a result of the U.S. Department of Energy's (DOE) environmental restoration and waste management activities, laboratories receive numerous analytical requests for gross α/β analyses. Traditional sample preparation methods for gross α/β analysis of environmental and mixed waste samples require repetitive leaching, which is time consuming and generates large volumes of secondary wastes. An alternative to leaching is microwave digestion. In the past. microwave technology has had limited application in the radiochemical laboratory because of restrictions on sample size resulting from vessel pressure limitations. However, new microwave vessel designs allow for pressures on the order of 11 MPa (1500 psi). A procedure is described in which microwave digestion is used to prepare environmental soil samples for gross α/β analysis. Results indicate that the described procedure meets performance requirements for several soil types and is equivalent to traditional digestion techniques. No statistical differences at the 95% confidence interval exist between the measurement on samples prepared from the hot plate and microwave digestion procedures for those soils tested. Moreover, microwave digestion allows samples to be prepared in a fraction of the time with significantly less acid and with lower potential of cross-contamination. In comparison to the traditional hot plate method, the waste volumes required for the microwave procedure are a factor of 10 lower, while the analyst time for sample processing is at least a factor of three lower

  18. Nuclear physics and heavy element research at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Stoyer, M A; Ahle, L E; Becker, J A; Bernstein, L A; Bleuel, D L; Burke, J T; Dashdorj, D; Henderson, R A; Hurst, A M; Kenneally, J M; Lesher, S R; Moody, K J; Nelson, S L; Norman, E B; Pedretti, M; Scielzo, N D; Shaughnessy, D A; Sheets, S A; Stoeffl, W; Stoyer, N J; Wiedeking, M; Wilk, P A; Wu, C Y

    2009-05-11

    This paper highlights some of the current basic nuclear physics research at Lawrence Livermore National Laboratory (LLNL). The work at LLNL concentrates on investigating nuclei at the extremes. The Experimental Nuclear Physics Group performs research to improve our understanding of nuclei, nuclear reactions, nuclear decay processes and nuclear astrophysics; an expertise utilized for important laboratory national security programs and for world-class peer-reviewed basic research.

  19. Development of positron diffraction and holography at LLNL

    International Nuclear Information System (INIS)

    Hamza, A.; Asoka-Kumar, P.; Stoeffl, W.; Howell, R.; Miller, D.; Denison, A.

    2003-01-01

    A low-energy positron diffraction and holography spectrometer is currently being constructed at the Lawrence Livermore National Laboratory (LLNL) to study surfaces and adsorbed structures. This instrument will operate in conjunction with the LLNL intense positron beam produced by the 100 MeV LINAC allowing data to be acquired in minutes rather than days. Positron diffraction possesses certain advantages over electron diffraction which are discussed. Details of the instrument based on that of low-energy electron diffraction are described

  20. The Minimization of Organic and Metallic Industrial Waste Via LEMNA MINOR Concentration

    Science.gov (United States)

    1992-12-30

    from municipal and industrial waste waters. Duckweed is a floating, widespread and fast-growing plant. It is smal, 3asy to cultivate and highly sensitive...and Cairns, J. Jr., "Accumulation and Depuration of Metals by Duckweed (Lemna perpusilla)," Ecotoxicology and Environmental Safety, 5, 87-96, 1981...to separate substances of different densities. calla: a plant of the arum family, native to South Africa, but cultivated in the United States, and

  1. Proceedings of waste stream minimization and utilization innovative concepts: An experimental technology exchange. Volume 1, Industrial solid waste processing municipal waste reduction/recycling

    Energy Technology Data Exchange (ETDEWEB)

    Lee, V.E. [ed.; Watts, R.L.

    1993-04-01

    This two-volume proceedings summarizes the results of fifteen innovations that were funded through the US Department of Energy`s Innovative Concept Program. The fifteen innovations were presented at the sixth Innovative Concepts Fair, held in Austin, Texas, on April 22--23, 1993. The concepts in this year`s fair address innovations that can substantially reduce or use waste streams. Each paper describes the need for the proposed concept, the concept being proposed, and the concept`s economics and market potential, key experimental results, and future development needs. The papers are divided into two volumes: Volume 1 addresses innovations for industrial solid waste processing and municipal waste reduction/recycling, and Volume 2 addresses industrial liquid waste processing and industrial gaseous waste processing. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  2. Minimal alteration of montmorillonite following long-term interaction with natural alkaline groundwater: Implications for geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Milodowski, Antoni E.; Norris, Simon; Alexander, W.Russell

    2016-01-01

    Bentonite is one of the more safety-critical components of the engineered barrier system in the disposal concepts developed for many types of radioactive waste. Bentonite is utilised because of its favourable properties which include plasticity, swelling capacity, colloid filtration, low hydraulic conductivity, high retardation of key radionuclides and stability in geological environments of relevance to waste disposal. However, bentonite is unstable under the highly alkaline conditions induced by Ordinary Portland Cement (OPC: initial porewater pH > 13) and this has driven interest in using low alkali cements (initial porewater pH9-11) as an alternative to OPC. To build a robust safety case for a repository for radioactive wastes, it is important to have supporting natural analogue data to confirm understanding of the likely long-term performance of bentonite in these lower alkali conditions. In Cyprus, the presence of natural bentonite in association with natural alkaline groundwater permits the zones of potential bentonite/alkaline water reaction to be studied as an analogy of the potential reaction between low alkali cement leachates and the bentonite buffer in the repository. Here, the results indicate that a cation diffusion front has moved some metres into the bentonite whereas the bentonite reaction front is restricted to a few millimetres into the clay. This reaction front shows minimal reaction of the bentonite (volumetrically, less than 1% of the bentonite), with production of a palygorskite secondary phase following reaction of the primary smectites over time periods of 10"5–10"6 years. - Highlights: • Alkaline porewaters from cement and concrete could destabilise bentonite buffer in a repository. • Evidence utilised to examine processes over repository timescales. • Alkaline water from the Troodos ophiolite reacts with bentonite. • Waters exchange Ca for Na on bentonite, smectite reacts to form palygorskite. • Observations indicate

  3. Removal of contaminants from equipment and debris and waste minimization using TechXtract{reg_sign} technology

    Energy Technology Data Exchange (ETDEWEB)

    Bonem, M.W. [EET, Inc., Bellaire, TX (United States)

    1997-10-01

    Under this Program Research and Development Agreement (PRDA), EET, Inc., is extending its proprietary TechXtract{reg_sign} chemical decontamination technology into an effective, economical, integrated contaminant removal system. This integrated system will consist of a series of decontamination baths using the TechXtract{reg_sign} chemical formulas, followed by a waste treatment process that will remove the contaminants from the spent chemicals. Sufficient decontamination will result so that materials can be released without restriction after they have been treated, even those materials that have traditionally been considered to be {open_quotes}undecontaminable.{close_quotes} The secondary liquid waste will then be treated to separate any hazardous and radioactive contaminants, so that the spent chemicals and wastewater can be discharged through conventional, permitted outlets. The TechXtract{reg_sign} technology is a unique process that chemically extracts hazardous contaminants from the surface and substrate of concrete, steel, and other solid materials. This technology has been used successfully to remove contaminants as varied as PCBs, radionuclides, heavy metals, and hazardous organics. The process` advantage over other alternatives is its effectiveness in safe and consistent extraction of subsurface contamination. TechXtract{reg_sign} is a proprietary process developed, owned, and provided by EET, Inc. The objective of the PRDA is to demonstrate on a full-scale basis an economical system for decontaminating equipment and debris, with further treatment of secondary waste streams to minimize waste volumes. Contaminants will be removed from the contaminated items to levels where they can be released for unrestricted use. The entire system will be designed with maximum flexibility and automation in mind.

  4. An interval-based possibilistic programming method for waste management with cost minimization and environmental-impact abatement under uncertainty.

    Science.gov (United States)

    Li, Y P; Huang, G H

    2010-09-15

    Considerable public concerns have been raised in the past decades since a large amount of pollutant emissions from municipal solid waste (MSW) disposal of processes pose risks on surrounding environment and human health. Moreover, in MSW management, various uncertainties exist in the related costs, impact factors and objectives, which can affect the optimization processes and the decision schemes generated. In this study, an interval-based possibilistic programming (IBPP) method is developed for planning the MSW management with minimized system cost and environmental impact under uncertainty. The developed method can deal with uncertainties expressed as interval values and fuzzy sets in the left- and right-hand sides of constraints and objective function. An interactive algorithm is provided for solving the IBPP problem, which does not lead to more complicated intermediate submodels and has a relatively low computational requirement. The developed model is applied to a case study of planning a MSW management system, where mixed integer linear programming (MILP) technique is introduced into the IBPP framework to facilitate dynamic analysis for decisions of timing, sizing and siting in terms of capacity expansion for waste-management facilities. Three cases based on different waste-management policies are examined. The results obtained indicate that inclusion of environmental impacts in the optimization model can change the traditional waste-allocation pattern merely based on the economic-oriented planning approach. The results obtained can help identify desired alternatives for managing MSW, which has advantages in providing compromised schemes under an integrated consideration of economic efficiency and environmental impact under uncertainty. Copyright 2010 Elsevier B.V. All rights reserved.

  5. Removal of contaminants from equipment and debris and waste minimization using TechXtract reg-sign technology

    International Nuclear Information System (INIS)

    Bonem, M.W.

    1997-01-01

    Under this Program Research and Development Agreement (PRDA), EET, Inc., is extending its proprietary TechXtract reg-sign chemical decontamination technology into an effective, economical, integrated contaminant removal system. This integrated system will consist of a series of decontamination baths using the TechXtract reg-sign chemical formulas, followed by a waste treatment process that will remove the contaminants from the spent chemicals. Sufficient decontamination will result so that materials can be released without restriction after they have been treated, even those materials that have traditionally been considered to be open-quotes undecontaminable.close quotes The secondary liquid waste will then be treated to separate any hazardous and radioactive contaminants, so that the spent chemicals and wastewater can be discharged through conventional, permitted outlets. The TechXtract reg-sign technology is a unique process that chemically extracts hazardous contaminants from the surface and substrate of concrete, steel, and other solid materials. This technology has been used successfully to remove contaminants as varied as PCBs, radionuclides, heavy metals, and hazardous organics. The process' advantage over other alternatives is its effectiveness in safe and consistent extraction of subsurface contamination. TechXtract reg-sign is a proprietary process developed, owned, and provided by EET, Inc. The objective of the PRDA is to demonstrate on a full-scale basis an economical system for decontaminating equipment and debris, with further treatment of secondary waste streams to minimize waste volumes. Contaminants will be removed from the contaminated items to levels where they can be released for unrestricted use. The entire system will be designed with maximum flexibility and automation in mind

  6. MSW management for waste minimization in Taiwan: The last two decades

    International Nuclear Information System (INIS)

    Lu, L.-T.; Hsiao, T.-Y.; Shang, N.-C.; Yu, Y.-H.; Ma, H.-W.

    2006-01-01

    Taiwan is the second most densely populated country in the world; its 22.604 million residents (2002) live in an area of 35,967 km 2 (628 people/km 2 ). Taiwan's economy has grown rapidly during the last 20 years, resulting in a corresponding increase in the amount of municipal solid waste (MSW). This study describes and evaluates the municipal solid waste management system in Taiwan. The study's results indicate that the amount of MSW began to decline after 1997, when the government enforced aggressive MSW management policies. By 2002, total MSW production had dropped by 27%, and the average daily per capita weight of MSW had fallen from 1.14 kg in 1997 to 0.81 kg in 2002. Summarizing the successful experience of MSW reduction in Taiwan, the most important factor was the government's combining of the MSW collection system with reduction/recycling programs. The second most important factor was the policy of extended producer responsibility, which laid a foundation of recycling by producers and retailers and promoted public recycling

  7. MSW management for waste minimization in Taiwan: the last two decades.

    Science.gov (United States)

    Lu, Li-Teh; Hsiao, Teng-Yuan; Shang, Neng-Chou; Yu, Yue-Hwa; Ma, Hwong-Wen

    2006-01-01

    Taiwan is the second most densely populated country in the world; its 22.604 million residents (2002) live in an area of 35,967 km2 (628 people/km2). Taiwan's economy has grown rapidly during the last 20 years, resulting in a corresponding increase in the amount of municipal solid waste (MSW). This study describes and evaluates the municipal solid waste management system in Taiwan. The study's results indicate that the amount of MSW began to decline after 1997, when the government enforced aggressive MSW management policies. By 2002, total MSW production had dropped by 27%, and the average daily per capita weight of MSW had fallen from 1.14 kg in 1997 to 0.81 kg in 2002. Summarizing the successful experience of MSW reduction in Taiwan, the most important factor was the government's combining of the MSW collection system with reduction/recycling programs. The second most important factor was the policy of extended producer responsibility, which laid a foundation of recycling by producers and retailers and promoted public recycling.

  8. Radioactive Waste Management Basis

    International Nuclear Information System (INIS)

    Perkins, B.K.

    2009-01-01

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

  9. Waste minimization and control: a review of problems and available technologies

    International Nuclear Information System (INIS)

    Butt, W.M.

    1999-01-01

    A country's environmental problems are affected by the level of its economic development, the availability of national resources, and the socio-economic level of this population. Poverty presents special problems for a heavily populated country with limited resources. environmental problems in Pakistan have become serious and should no longer be neglected. These relate air and water pollution particularly in metropolitan and industrial zones, degradation of common property sources which affect the poor adversely due to the degradation of their life support system, threat to biodiversity, inadequate system of solid waste disposal and sanitation with consequent adverse impact on health, infant mortality, birth rate. These problems impose a serious cost on society although it is impossible to comprehend the extent of these on costs. (author)

  10. Evaluation of radwaste minimization program of dry and wet active waste in the Laguna Verde Nuclear Power Plant

    International Nuclear Information System (INIS)

    Luna-Garza, Hector

    2001-01-01

    A growing rate of radwaste volume production combined with an increase of both, costs and associated dose involved in its treatment and disposition processes have created a serious problem to the Laguna Verde Nuclear Power Plant (BWR, two Units, 682 Mwe each) in Mexico. Due the lack of a Final Repository in the country, the solution in the short or long terms relies on the success of a continuous and aggressive minimization program mainly based on modifications and upgrades applied to these processes. Technical and administrative strategies adopted by LVNPP for the reduction of Liquid Effluents and Dry and Wet Active Waste in the next three years are described. Based on the results of the LVNPP current radwaste process systems, an estimated accumulation of 11,502 m 3 by the year 2035 will exceed the actual on-site storage capacity. If the strategies succeed, this production would fall to an expected manageable volume of 4067 m 3 . (author)

  11. Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Balkey, J.J.; Robinson, M.A.; Boak, J.

    1997-12-01

    The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO{sub 2}, Mg(OH){sub 2} precipitation, supercritical H{sub 2}O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination & Decommissioning (D&D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations.

  12. Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Balkey, J.J.; Robinson, M.A.; Boak, J.

    1997-01-01

    The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO 2 , Mg(OH) 2 precipitation, supercritical H 2 O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination ampersand Decommissioning (D ampersand D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations

  13. Evaluation of select trade-offs between ground-water remediation and waste minimization for petroleum refining industry

    International Nuclear Information System (INIS)

    Andrews, C.D.; McTernan, W.F.; Willett, K.K.

    1996-01-01

    An investigation comparing environmental remediation alternatives and attendant costs for a hypothetical refinery site located in the Arkansas River alluvium was completed. Transport from the land's surface to and through the ground water of three spill sizes was simulated, representing a base case and two possible levels of waste minimization. Remediation costs were calculated for five alternative remediation options, for three possible regulatory levels and alternative site locations, for four levels of technology improvement, and for eight different years. It is appropriate from environmental and economic perspectives to initiate significant efforts and expenditures that are necessary to minimize the amount and type of waste produced and disposed during refinery operations; or conversely, given expected improvements in technology, is it better to wait until remediation technologies improve, allowing greater environmental compliance at lower costs? The present work used deterministic models to track a light nonaqueous phase liquid (LNAPL) spill through the unsaturated zone to the top of the water table. Benzene leaching from LNAPL to the ground water was further routed through the alluvial aquifer. Contaminant plumes were simulated over 50 yr of transport and remediation costs assigned for each of the five treatment options for each of these years. The results of these efforts show that active remediation is most cost effective after a set point or geochemical quasi-equilibrium is reached, where long-term improvements in technology greatly tilt the recommended option toward remediation. Finally, the impacts associated with increasingly rigorous regulatory levels present potentially significant penalties for the remediation option, but their likelihood of occurrence is difficult to define

  14. Minimizing the Moisture Damage and Drain down of Iraqi SMA Mixtures Using Waste Additives

    Directory of Open Access Journals (Sweden)

    Ali Al-Hadidy

    2013-04-01

    Full Text Available This research deals with the viability of using polyester fiber (PF, crumb rubber tire (CRT and cellulose fiber (CF as stabilizing waste additives in producing Iraqi SMA mixtures that sustain drain down phenomenon and moisture damage sensitivity. Different ratios of these additives (0.1, 0.2, and 0.3% by weight of aggregate and filler were mixed with 40/50 paving asphalt by means of dry process. Unmodified and modified SMA mixtures were subjected to drain down, Marshall, static indirect tensile strength, tensile stiffness modulus, static compressive strength, tensile strength ratio and index of retained strength tests. A set of regression equations between these tests were established. In addition, an optimization table based on these tests, which can be used to select the type or amount of additive for any field applications has been determined and reported. The results indicated that the inclusion of these additives in SMA mixtures can satisfy the performance requirement of high temperature and much rain zone.

  15. Minimizing draining waste through extending the lifetime of pilot jobs in Grid environments

    International Nuclear Information System (INIS)

    Sfiligoi, I; Martin, T; Würthwein, F; Bockelman, B P; Bradley, D C

    2014-01-01

    The computing landscape is moving at an accelerated pace to many-core computing. Nowadays, it is not unusual to get 32 cores on a single physical node. As a consequence, there is increased pressure in the pilot systems domain to move from purely single-core scheduling and allow multi-core jobs as well. In order to allow for a gradual transition from single-core to multi-core user jobs, it is envisioned that pilot jobs will have to handle both kinds of user jobs at the same time, by requesting several cores at a time from Grid providers and then partitioning them between the user jobs at runtime. Unfortunately, the current Grid ecosystem only allows for relatively short lifetime of pilot jobs, requiring frequent draining, with the relative waste of compute resources due to varying lifetimes of the user jobs. Significantly extending the lifetime of pilot jobs is thus highly desirable, but must come without any adverse effects for the Grid resource providers. In this paper we present a mechanism, based on communication between the pilot jobs and the Grid provider, that allows for pilot jobs to run for extended periods of time when there are available resources, but also allows the Grid provider to reclaim the resources in a short amount of time when needed. We also present the experience of running a prototype system using the above mechanism on a few US-based Grid sites.

  16. Waste minimization and pollution prevention technology transfer : the Airlie House Projects

    International Nuclear Information System (INIS)

    Gatrone, R.; McHenry, J.; Myron, H.; Thout, J. R.

    1998-01-01

    The Airlie House Pollution Prevention Technology Transfer Projects were a series of pilot projects developed for the US Department of Energy with the intention of transferring pollution prevention technology to the private sector. The concept was to develop small technology transfer initiatives in partnership with the private sector. Argonne National Laboratory developed three projects: the microscale chemistry in education project, the microscale cost benefit study project, and the Bethel New Life recycling trainee project. The two microscale chemistry projects focused on introducing microscale chemistry technologies to secondary and college education. These programs were inexpensive to develop and received excellent evaluations from participants and regulators. The Bethel New Life recycling trainee project provided training for two participants who helped identify recycling and source reduction opportunities in Argonne National Laboratory's solid waste stream. The pilot projects demonstrated that technology transfer initiatives can be developed and implemented with a small budget and within a short period of time. The essential components of the pilot projects were identifying target technologies that were already available, identifying target audiences, and focusing on achieving a limited but defined objective

  17. Petroleum industry is cleaning up its act -- Self-cleaning filters to maximize profits, minimize waste and reduce liability

    International Nuclear Information System (INIS)

    Williams, D.

    2004-01-01

    Recent steps taken by the petroleum industry to control end-of-pipe pollution and to minimize waste at the source by changing over to self-cleaning, backwashable filters instead of the traditional disposable filters such as bags or cartridges, are discussed. Various self-cleaning filter systems and their advantages are described, using REACTOGARD which provides total protection for catalysts in fixed-bed reactors and EROSIONGARD, used in fluidized catalytic crackers, as examples. Both filter systems have been developed by RPA Process Technologies, Inc., a global leader in industrial filtration systems. Major advantages attributed to self-cleaning filters include significantly reduced costs through reducing the number of catalyst change-out cycles, maximized platform productivity through virtually eliminating the risk of plugged wells, reduced waste through ability to recycle cleaning liquids, increased profits through shorter return-on-investment cycles, reduced emissions and reduced future liability through higher safety in the workplace; also reduced pollution of landfill sites. 1 photo

  18. Conversion of finished leather waste incorporated with plant fibers into value added consumer products - An effort to minimize solid waste in Ethiopia.

    Science.gov (United States)

    Teklay, A; Gebeyehu, G; Getachew, T; Yaynshet, T; Sastry, T P

    2017-10-01

    Presently, the leftovers from leather product industries are discarded as waste in Ethiopia. The objective of the present study was therefore, to prepare composite sheets by incorporating various plant fibers like enset (Ensete ventricosum), hibiscus (Hibiscus cannabinus), jute (Corchorus trilocularis L.), palm (Phoenix dactylifera) and sisal (Agave sisal) in various proportions into the leather waste. Resin binder (RB) and natural rubber latex (NRL) were used as binding agents for the preparation of the composite sheets. The composite sheets prepared were characterized for their physicochemical properties (tensile strength, elongation at break, stitch tear strength, water absorption, water desorption and flexing strength). Composite sheets prepared using RB having 10% hibiscus, 20% palm and 40% sisal fibers showed better mechanical properties than their respective controls. In composite sheets prepared using NRL having 30% jute fiber exhibited better mechanical properties than its control. Most of the plant fibers used in this study played a role in increasing the performance of the sheets. However, as seen from the results, the contribution of these plant fibers on performance of the composite sheets prepared is dependent on the ratio used and the nature of binder. The SEM studies have exhibited the composite nature of the sheets and FTIR studies have shown the functional groups of collagen protein, cellulose and binders. The prepared sheets were used as raw materials for preparation of items like stiff hand bags, ladies' purse, keychain, chappal upper, wallet, wall cover, mouse pad and other interior decorating products. By preparing such value added products, we can reduce solid waste; minimize environmental pollution and thereby securing environmental sustainability. Copyright © 2017 Elsevier Ltd. All rights reserved.

  19. Diversification and strategic management of LLNL's R ampersand D portfolio

    International Nuclear Information System (INIS)

    Glinsky, M.E.

    1994-12-01

    Strategic management of LLNL's research effort is addressed. A general framework is established by presenting the McKinsey/BCG Matrix Analysis as it applies to the research portfolio. The framework is used to establish the need for the diversification into new attractive areas of research and for the improvement of the market position of existing research in those attractive areas. With the need for such diversification established, attention is turned to optimizing it. There are limited resources available. It is concluded that LLNL should diversify into only a few areas and try to obtain full market share as soon as possible

  20. Thermochemical hydrogen production studies at LLNL: a status report

    International Nuclear Information System (INIS)

    Krikorian, O.H.

    1982-01-01

    Currently, studies are underway at the Lawrence Livermore National Laboratory (LLNL) on thermochemical hydrogen production based on magnetic fusion energy (MFE) and solar central receivers as heat sources. These areas of study were described earlier at the previous IEA Annex I Hydrogen Workshop (Juelich, West Germany, September 23-25, 1981), and a brief update will be given here. Some basic research has also been underway at LLNL on the electrolysis of water from fused phosphate salts, but there are no current results in that area, and the work is being terminated

  1. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    Energy Technology Data Exchange (ETDEWEB)

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

    2013-07-01

    determine the TRU content of the boxes by assessing the activity of Am-241 (59 keV) and Pu-241 (414 keV). Using the data generated it was possible for qualified subject matter experts (SME) to assess that the gloveboxes could be consigned for disposition as LLW and not as TRU. Once this determination was assessed and accepted the gloveboxes were prepared for final disposition to the Nevada National Security Site (NNSS) - formerly the Nevada Test Site (NTS). This preparation involved fixing any remaining radioactive contamination within the gloveboxes by filling them with a foam compound, prior to transportation. Once the remaining contamination was fixed the gloveboxes were removed from the laboratory and prepared for transported by road to NNSS. This successful glovebox decontamination and decommissioning process illustrates the means by which TRU waste generation has been minimized, LLW generation has been maximized, and risk has been effectively managed. The process minimizes the volume of TRU waste and reduced the decommissioning time with significant cost savings as the result. (authors)

  2. A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634

    International Nuclear Information System (INIS)

    Pancake, Daniel; Rock, Cynthia M.; Creed, Richard; Donohoue, Tom; Martin, E. Ray; Mason, John A.; Norton, Christopher J.; Crosby, Daniel; Nachtman, Thomas J.

    2013-01-01

    determine the TRU content of the boxes by assessing the activity of Am-241 (59 keV) and Pu-241 (414 keV). Using the data generated it was possible for qualified subject matter experts (SME) to assess that the gloveboxes could be consigned for disposition as LLW and not as TRU. Once this determination was assessed and accepted the gloveboxes were prepared for final disposition to the Nevada National Security Site (NNSS) - formerly the Nevada Test Site (NTS). This preparation involved fixing any remaining radioactive contamination within the gloveboxes by filling them with a foam compound, prior to transportation. Once the remaining contamination was fixed the gloveboxes were removed from the laboratory and prepared for transported by road to NNSS. This successful glovebox decontamination and decommissioning process illustrates the means by which TRU waste generation has been minimized, LLW generation has been maximized, and risk has been effectively managed. The process minimizes the volume of TRU waste and reduced the decommissioning time with significant cost savings as the result. (authors)

  3. Spill exercise 1980: an LLNL emergency training exercise

    International Nuclear Information System (INIS)

    Morse, J.L.; Gibson, T.A.; Vance, W.F.

    1981-01-01

    An emergency training exercise at Lawrence Livermore National Laboratory (LLNL) demonstrated that off-hours emergency personnel can respond promptly and effecively to an emergency situation involving radiation, hazardous chemicals, and injured persons. The exercise simulated an explosion in a chemistry laboratory and a subsequent toxic-gas release

  4. Capabilities required to conduct the LLNL plutonium mission

    International Nuclear Information System (INIS)

    Kass, J.; Bish, W.; Copeland, A.; West, J.; Sack, S.; Myers, B.

    1991-01-01

    This report outlines the LLNL plutonium related mission anticipated over the next decade and defines the capabilities required to meet that mission wherever the Plutonium Facility is located. If plutonium work is relocated to a place where the facility is shared, then some capabilities can be commonly used by the sharing parties. However, it is essential that LLNL independently control about 20000 sq ft of net lab space, filled with LLNL controlled equipment, and staffed by LLNL employees. It is estimated that the cost to construct this facility should range from $140M to $200M. Purchase and installation of equipment to replace that already in Bldg 332 along with additional equipment identified as being needed to meet the mission for the next ten to fifteen years, is estimated to cost $118M. About $29M of the equipment could be shared. The Hardened Engineering Test Building (HETB) with its additional 8000 sq ft of unique test capability must also be replaced. The fully equipped replacement cost is estimated to be about $10M. About 40000 sq ft of setup and support space are needed along with office and related facilities for a 130 person resident staff. The setup space is estimated to cost $8M. The annual cost of a 130 person resident staff (100 programmatic and 30 facility operation) is estimated to be $20M

  5. Proceedings of the LLNL Technical Women`s Symposium

    Energy Technology Data Exchange (ETDEWEB)

    von Holtz, E. [ed.

    1993-12-31

    This report documents events of the LLNL Technical Women`s Symposium. Topics include; future of computer systems, environmental technology, defense and space, Nova Inertial Confinement Fusion Target Physics, technical communication, tools and techniques for biology in the 1990s, automation and robotics, software applications, materials science, atomic vapor laser isotope separation, technical communication, technology transfer, and professional development workshops.

  6. Proceedings of the LLNL technical women`s symposium

    Energy Technology Data Exchange (ETDEWEB)

    von Holtz, E. [ed.

    1994-12-31

    Women from institutions such as LLNL, LBL, Sandia, and SLAC presented papers at this conference. The papers deal with many aspects of global security, global ecology, and bioscience; they also reflect the challenges faced in improving business practices, communicating effectively, and expanding collaborations in the industrial world. Approximately 87 ``abstracts`` are included in six sessions; more are included in the addendum.

  7. The design and implementation of the LLNL gigabit testbed

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, D. [Lawrence Livermore National Labs., CA (United States)

    1994-12-01

    This paper will look at the design and implementation of the LLNL Gigabit testbed (LGTB), where various high speed networking products, can be tested in one environment. The paper will discuss the philosophy behind the design of and the need for the testbed, the tests that are performed in the testbed, and the tools used to implement those tests.

  8. LLNL X-ray Calibration and Standards Laboratory

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The LLNL X-ray Calibration and Standards Laboratory is a unique facility for developing and calibrating x-ray sources, detectors, and materials, and for conducting x-ray physics research in support of our weapon and fusion-energy programs

  9. Evidence-based integrated environmental solutions for secondary lead smelters: Pollution prevention and waste minimization technologies and practices

    Energy Technology Data Exchange (ETDEWEB)

    Genaidy, A.M., E-mail: world_tek_inc@yahoo.com [University of Cincinnati, Cincinnati, Ohio (United States); Sequeira, R. [University of Cincinnati, Cincinnati, Ohio (United States); Tolaymat, T. [U.S. Environmental Protection Agency, Office of Research and Development, Cincinnati, Ohio (United States); Kohler, J. [US Environmental Protection Agency, Office of Solid Waste and Emergency Response, Washington DC (United States); Rinder, M. [WorldTek Inc, Cincinnati (United States)

    2009-05-01

    An evidence-based methodology was adopted in this research to establish strategies to increase lead recovery and recycling via a systematic review and critical appraisal of the published literature. In particular, the research examines pollution prevention and waste minimization practices and technologies that meet the following criteria: (a) reduce/recover/recycle the largest quantities of lead currently being disposed of as waste, (b) technically and economically viable, that is, ready to be diffused and easily transferable, and (c) strong industry interest (i.e., industry would consider implementing projects with higher payback periods). The following specific aims are designed to achieve the study objectives: Aim 1 - To describe the recycling process of recovering refined lead from scrap; Aim 2 - To document pollution prevention and waste management technologies and practices adopted by US stakeholders along the trajectory of LAB and lead product life cycle; Aim 3 - To explore improved practices and technologies which are employed by other organizations with an emphasis on the aforementioned criteria; Aim 4 - To demonstrate the economic and environmental costs and benefits of applying improved technologies and practices to existing US smelting operations; and Aim 5 - To evaluate improved environmental technologies and practices using an algorithm that integrates quantitative and qualitative criteria. The process of identifying relevant articles and reports was documented. The description of evidence was presented for current practices and technologies used by US smelters as well as improved practices and technologies. Options for integrated environmental solutions for secondary smelters were introduced and rank ordered on the basis of costs (i.e., capital investment) and benefits (i.e., production increases, energy and flux savings, and reduction of SO2 and slag). An example was provided to demonstrate the utility of the algorithm by detailing the costs and

  10. Evidence-based integrated environmental solutions for secondary lead smelters: pollution prevention and waste minimization technologies and practices.

    Science.gov (United States)

    Genaidy, A M; Sequeira, R; Tolaymat, T; Kohler, J; Rinder, M

    2009-05-01

    An evidence-based methodology was adopted in this research to establish strategies to increase lead recovery and recycling via a systematic review and critical appraisal of the published literature. In particular, the research examines pollution prevention and waste minimization practices and technologies that meet the following criteria: (a) reduce/recover/recycle the largest quantities of lead currently being disposed of as waste, (b) technically and economically viable, that is, ready to be diffused and easily transferable, and (c) strong industry interest (i.e., industry would consider implementing projects with higher payback periods). The following specific aims are designed to achieve the study objectives: Aim 1 - To describe the recycling process of recovering refined lead from scrap; Aim 2 - To document pollution prevention and waste management technologies and practices adopted by US stakeholders along the trajectory of LAB and lead product life cycle; Aim 3 - To explore improved practices and technologies which are employed by other organizations with an emphasis on the aforementioned criteria; Aim 4 - To demonstrate the economic and environmental costs and benefits of applying improved technologies and practices to existing US smelting operations; and Aim 5 - To evaluate improved environmental technologies and practices using an algorithm that integrates quantitative and qualitative criteria. The process of identifying relevant articles and reports was documented. The description of evidence was presented for current practices and technologies used by US smelters as well as improved practices and technologies. Options for integrated environmental solutions for secondary smelters were introduced and rank ordered on the basis of costs (i.e., capital investment) and benefits (i.e., production increases, energy and flux savings, and reduction of SO(2) and slag). An example was provided to demonstrate the utility of the algorithm by detailing the costs and

  11. Mixed Waste Management Facility

    International Nuclear Information System (INIS)

    Brummond, W.; Celeste, J.; Steenhoven, J.

    1993-08-01

    The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE

  12. Final Report: Fiscal Year 1997 demonstration of omnivorous non-thermal mixed waste treatment: Direct chemical oxidation of organic solids and liquids using peroxydisulfate

    International Nuclear Information System (INIS)

    Cooper, J.F.; Ballazs G.B.

    1998-01-01

    Direct Chemical Oxidation (DCO) is a non-thermal, ambient pressure, aqueous-based technology for the oxidative destruction of the organic components of hazardous or mixed waste streams. The process has been developed for applications in waste treatment, chemical demilitarization and decontamination at LLNL since 1992. The process uses solutions of the peroxydisulfate ion (typically sodium or ammonium salts) to completely mineralize the organics to carbon dioxide and water. The expended oxidant may be electrolytically regenerated to minimize secondary waste. The paper briefly describes: free radical and secondary oxidant formation; electrochemical regeneration; offgas stream; and throughput

  13. Final Report: Fiscal Year 1997 demonstration of omnivorous non-thermal mixed waste treatment: Direct chemical oxidation of organic solids and liquids using peroxydisulfate

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, J.F.

    1998-01-01

    Direct Chemical Oxidation (DCO) is a non-thermal, ambient pressure, aqueous-based technology for the oxidative destruction of the organic components of hazardous or mixed waste streams. The process has been developed for applications in waste treatment, chemical demilitarization and decontamination at LLNL since 1992. The process uses solutions of the peroxydisulfate ion (typically sodium or ammonium salts) to completely mineralize the organics to carbon dioxide and water. The expended oxidant may be electrolytically regenerated to minimize secondary waste. The paper briefly describes: free radical and secondary oxidant formation; electrochemical regeneration; offgas stream; and throughput.

  14. A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors

    Directory of Open Access Journals (Sweden)

    E. Bomboni

    2008-01-01

    Full Text Available This paper presents a critical review of the recent improvements in minimizing nuclear waste in terms of quantities, long-term activities, and radiotoxicities by innovative GCRs, with particular emphasis to the results obtained at the University of Pisa. Regarding these last items, in the frame of some EU projects (GCFR, PUMA, and RAPHAEL, we analyzed symbiotic fuel cycles coupling current LWRs with HTRs, finally closing the cycle by GCFRs. Particularly, we analyzed fertile-free and Pu-Th-based fuel in HTR: we improved plutonium exploitation also by optimizing Pu/Th ratios in the fuel loaded in an HTR. Then, we chose GCFRs to burn residual MA. We have started the calculations on simplified models, but we ended them using more “realistic” models of the reactors. In addition, we have added the GCFR multiple recycling option using keff calculations for all the reactors. As a conclusion, we can state that, coupling HTR with GCFR, the geological disposal issues concerning high-level radiotoxicity of MA can be considerably reduced.

  15. Waste management and climate protection. Contribution of Bavarian waste management for greenhouse gas minimization; Abfallwirtschaft und Klimaschutz. Beitrag der bayerischen Abfallwirtschaft zur Treibhausgas-Minderung

    Energy Technology Data Exchange (ETDEWEB)

    Peche, R.; Kreibe, S. [bifa Umweltinstitut, Augsburg (Germany)

    2007-08-15

    bifa created a material flow model for approximately 23 million tons of Bavarian municipal and industrial waste that incorporates collection of waste, waste disposal and processing and treatment of residual material. bifa determined the influence of these material flows on emissions of greenhouse gases. The analysis shows that the Bavarian waste management achieved a reduction of greenhouse gases in the municipal and industrial waste sector that amounted to 3.2 million tons of carbon dioxide equivalents (CO{sub 2}E) in 2003, thus reducing environmental impact considerably. To see the overall reduction of greenhouse gases it is however necessary to compare the system of waste collection, waste treatment and waste processing with a fictitious scenario of waste disposal exclusively via landfill. This would cause an environmental load of 9.58 million tons CO{sub 2}E. Together with the amount of reduction attained in 2003, an overall reduction of greenhouse gas emissions of 12.78 millions tons CO{sub 2}E has thus been achieved by the Bavarian waste management. Analysis of possible future waste processing and waste avoidance measures showed two areas with significant additional potential for the reduction of greenhouse gas emissions. One is waste avoidance - e. g. through increased municipal counselling - however, this is difficult to realize. The other possibility is the optimisation of bio-waste processing. (orig.)

  16. LLNL Mercury Project Trinity Open Science Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Brantley, Patrick [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dawson, Shawn [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McKinley, Scott [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); O' Brien, Matt [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Peters, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pozulp, Mike [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Becker, Greg [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mohror, Kathryn [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Moody, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-04-20

    The Mercury Monte Carlo particle transport code developed at Lawrence Livermore National Laboratory (LLNL) is used to simulate the transport of radiation through urban environments. These challenging calculations include complicated geometries and require significant computational resources to complete. As a result, a question arises as to the level of convergence of the calculations with Monte Carlo simulation particle count. In the Trinity Open Science calculations, one main focus was to investigate convergence of the relevant simulation quantities with Monte Carlo particle count to assess the current simulation methodology. Both for this application space but also of more general applicability, we also investigated the impact of code algorithms on parallel scaling on the Trinity machine as well as the utilization of the Trinity DataWarp burst buffer technology in Mercury via the LLNL Scalable Checkpoint/Restart (SCR) library.

  17. Seismic evaluation of the LLNL plutonium facility (Building 332)

    International Nuclear Information System (INIS)

    Hall, W.J.; Sozen, M.A.

    1982-03-01

    The expected performance of the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (Building 332) subjected to earthquake ground motion has been evaluated. Anticipated behavior of the building, glove boxes, ventilation system and other systems critical for containment of plutonium is described for three severe postulated earthquake excitations. Based upon this evaluation, some damage to the building, glove boxes and ventilation system would be expected but no collapse of any structure is anticipated as a result of the postulated earthquake ground motions

  18. Probabilistic Seismic Hazards Update for LLNL: PSHA Results Report

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Alfredo [Fugro Consultants, Inc., Houston, TX (United States); Altekruse, Jason [Fugro Consultants, Inc., Houston, TX (United States); Menchawi, Osman El [Fugro Consultants, Inc., Houston, TX (United States)

    2016-03-11

    This report presents the Probabilistic Seismic Hazard Analysis (PSHA) performed for Building 332 at the Lawrence Livermore National Laboratory (LLNL), near Livermore, CA by Fugro Consultants, Inc. (FCL). This report is specific to Building 332 only and not to other portions of the Laboratory. The study performed for the LLNL site includes a comprehensive review of recent information relevant to the LLNL regional tectonic setting and regional seismic sources in the vicinity of the site and development of seismic wave transmission characteristics. The Seismic Source Characterization (SSC), documented in Project Report No. 2259-PR-02 (FCL, 2015a), and Ground Motion Characterization (GMC), documented in Project Report No. 2259-PR-06 (FCL, 2015c) were developed in accordance with ANS/ANSI 2.29-2008 Level 2 PSHA guidelines. The ANS/ANSI 2.29-2008 Level 2 PSHA framework is documented in Project Report No. 2259-PR-05 (FCL, 2016a). The Hazard Input Document (HID) for input into the PSHA developed from the SSC is presented in Project Report No. 2259-PR-04 (FCL, 2016b). The site characterization used as input for development of the idealized site profiles including epistemic uncertainty and aleatory variability is presented in Project Report No. 2259-PR-03 (FCL, 2015b).

  19. GAMA-LLNL Alpine Basin Special Study: Scope of Work

    Energy Technology Data Exchange (ETDEWEB)

    Singleton, M J; Visser, A; Esser, B K; Moran, J E

    2011-12-12

    For this task LLNL will examine the vulnerability of drinking water supplies in foothills and higher elevation areas to climate change impacts on recharge. Recharge locations and vulnerability will be determined through examination of groundwater ages and noble gas recharge temperatures in high elevation basins. LLNL will determine whether short residence times are common in one or more subalpine basin. LLNL will measure groundwater ages, recharge temperatures, hydrogen and oxygen isotopes, major anions and carbon isotope compositions on up to 60 samples from monitoring wells and production wells in these basins. In addition, a small number of carbon isotope analyses will be performed on surface water samples. The deliverable for this task will be a technical report that provides the measured data and an interpretation of the data from one or more subalpine basins. Data interpretation will: (1) Consider climate change impacts to recharge and its impact on water quality; (2) Determine primary recharge locations and their vulnerability to climate change; and (3) Delineate the most vulnerable areas and describe the likely impacts to recharge.

  20. Regulatory Strategies To Minimize Generation Of Regulated Wastes From Cleanup, Continued Use Or Decommissioning Of Nuclear Facilities Contaminated With Polychlorinated Biphenyls (PCBS) - 11198

    International Nuclear Information System (INIS)

    Lowry, N.

    2010-01-01

    Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of (ge) 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste

  1. Radioactive Waste Management BasisApril 2006

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  2. Incorporation of gypsum waste in ceramic block production: Proposal for a minimal battery of tests to evaluate technical and environmental viability of this recycling process.

    Science.gov (United States)

    Godinho-Castro, Alcione P; Testolin, Renan C; Janke, Leandro; Corrêa, Albertina X R; Radetski, Claudemir M

    2012-01-01

    Civil engineering-related construction and demolition debris is an important source of waste disposed of in municipal solid waste landfills. After clay materials, gypsum waste is the second largest contributor to the residential construction waste stream. As demand for sustainable building practices grows, interest in recovering gypsum waste from construction and demolition debris is increasing, but there is a lack of standardized tests to evaluate the technical and environmental viability of this solid waste recycling process. By recycling gypsum waste, natural deposits of gypsum might be conserved and high amounts of the waste by-product could be reused in the civil construction industry. In this context, this paper investigates a physical property (i.e., resistance to axial compression), the chemical composition and the ecotoxicological potential of ceramic blocks constructed with different proportions of clay, cement and gypsum waste, and assesses the feasibility of using a minimal battery of tests to evaluate the viability of this recycling process. Consideration of the results for the resistance to axial compression tests together with production costs revealed that the best formulation was 35% of plastic clay, 35% of non-plastic clay, 10% of Portland cement and 20% of gypsum waste, which showed a mean resistance of 4.64MPa. Energy dispersive X-ray spectrometry showed calcium and sulfur to be the main elements, while quartz, gypsum, ettringite and nacrite were the main crystalline compounds found in this formulation. Ecotoxicity tests showed that leachate from this formulation is weakly toxic toward daphnids and bacteria (EC(20%)=69.0 and 75.0, respectively), while for algae and fish the leachate samples were not toxic at the EC(50%) level. Overall, these results show that the addition of 20% of gypsum waste to the ceramic blocks could provide a viable substitute for clay in the ceramics industry and the tests applied in this study proved to be a useful tool

  3. 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

  4. Description and application of the AERIN Code at LLNL

    International Nuclear Information System (INIS)

    King, W.C.

    1986-01-01

    The AERIN code was written at the Lawrence Livermore National Laboratory in 1976 to compute the organ burdens and absorbed dose resulting from a chronic or acute inhalation of transuranic isotopes. The code was revised in 1982 to reflect the concepts of ICRP-30. This paper will describe the AERIN code and how it has been used at LLNL to study more than 80 cases of internal deposition and obtain estimates of internal dose. A comparison with the computed values of the committed organ dose is made with ICRP-30 values. The benefits of using the code are described. 3 refs., 3 figs., 6 tabs

  5. Final report on the LLNL compact torus acceleration project

    International Nuclear Information System (INIS)

    Eddleman, J.; Hammer, J.; Hartman, C.; McLean, H.; Molvik, A.

    1995-01-01

    In this report, we summarize recent work at LLNL on the compact torus (CT) acceleration project. The CT accelerator is a novel technique for projecting plasmas to high velocities and reaching high energy density states. The accelerator exploits magnetic confinement in the CT to stably transport plasma over large distances and to directed kinetic energies large in comparison with the CT internal and magnetic energy. Applications range from heating and fueling magnetic fusion devices, generation of intense pulses of x-rays or neutrons for weapons effects and high energy-density fusion concepts

  6. Guidelines for the disposal of dangerous and toxic wastes so as to minimize or prevent environmental and water pollution

    CSIR Research Space (South Africa)

    Rudd, RT

    1978-01-01

    Full Text Available Modern society is producing ever increasing quantities of dangerous and/or toxic wastes, which require safe and effective disposal if they are not to pose a threat to our water supplies or the environment in general....

  7. Radioactive Waste Management BasisSept 2001

    International Nuclear Information System (INIS)

    Goodwin, S.S.

    2011-01-01

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  8. Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

    International Nuclear Information System (INIS)

    Wall, Mark A.

    2016-01-01

    The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

  9. Author Contribution to the Pu Handbook II: Chapter 37 LLNL Integrated Sample Preparation Glovebox (TEM) Section

    Energy Technology Data Exchange (ETDEWEB)

    Wall, Mark A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-10-25

    The development of our Integrated Actinide Sample Preparation Laboratory (IASPL) commenced in 1998 driven by the need to perform transmission electron microscopy studies on naturally aged plutonium and its alloys looking for the microstructural effects of the radiological decay process (1). Remodeling and construction of a laboratory within the Chemistry and Materials Science Directorate facilities at LLNL was required to turn a standard radiological laboratory into a Radiological Materials Area (RMA) and Radiological Buffer Area (RBA) containing type I, II and III workplaces. Two inert atmosphere dry-train glove boxes with antechambers and entry/exit fumehoods (Figure 1), having a baseline atmosphere of 1 ppm oxygen and 1 ppm water vapor, a utility fumehood and a portable, and a third double-walled enclosure have been installed and commissioned. These capabilities, along with highly trained technical staff, facilitate the safe operation of sample preparation processes and instrumentation, and sample handling while minimizing oxidation or corrosion of the plutonium. In addition, we are currently developing the capability to safely transfer small metallographically prepared samples to a mini-SEM for microstructural imaging and chemical analysis. The gloveboxes continue to be the most crucial element of the laboratory allowing nearly oxide-free sample preparation for a wide variety of LLNL-based characterization experiments, which includes transmission electron microscopy, electron energy loss spectroscopy, optical microscopy, electrical resistivity, ion implantation, X-ray diffraction and absorption, magnetometry, metrological surface measurements, high-pressure diamond anvil cell equation-of-state, phonon dispersion measurements, X-ray absorption and emission spectroscopy, and differential scanning calorimetry. The sample preparation and materials processing capabilities in the IASPL have also facilitated experimentation at world-class facilities such as the

  10. A Novel Approach to Semantic and Coreference Annotation at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Firpo, M

    2005-02-04

    A case is made for the importance of high quality semantic and coreference annotation. The challenges of providing such annotation are described. Asperger's Syndrome is introduced, and the connections are drawn between the needs of text annotation and the abilities of persons with Asperger's Syndrome to meet those needs. Finally, a pilot program is recommended wherein semantic annotation is performed by people with Asperger's Syndrome. The primary points embodied in this paper are as follows: (1) Document annotation is essential to the Natural Language Processing (NLP) projects at Lawrence Livermore National Laboratory (LLNL); (2) LLNL does not currently have a system in place to meet its need for text annotation; (3) Text annotation is challenging for a variety of reasons, many related to its very rote nature; (4) Persons with Asperger's Syndrome are particularly skilled at rote verbal tasks, and behavioral experts agree that they would excel at text annotation; and (6) A pilot study is recommend in which two to three people with Asperger's Syndrome annotate documents and then the quality and throughput of their work is evaluated relative to that of their neuro-typical peers.

  11. LLNL (Lawrence Livermore National Laboratory) research on cold fusion

    Energy Technology Data Exchange (ETDEWEB)

    Thomassen, K I; Holzrichter, J F [eds.

    1989-09-14

    With the appearance of reports on Cold Fusion,'' scientists at the Lawrence Livermore National Laboratory (LLNL) began a series of increasingly sophisticated experiments and calculations to explain these phenomena. These experiments can be categorized as follows: (a) simple experiments to replicate the Utah results, (b) more sophisticated experiments to place lower bounds on the generation of heat and production of nuclear products, (c) a collaboration with Texas A M University to analyze electrodes and electrolytes for fusion by-products in a cell producing 10% excess heat (we found no by-products), and (d) attempts to replicate the Frascati experiment that first found neutron bursts when high-pressure deuterium gas in a cylinder with Ti chips was temperature-cycled. We failed in categories (a) and (b) to replicate either the Pons/Fleischmann or the Jones phenomena. We have seen phenomena similar to the Frascati results, (d) but these low-level burst signals may not be coming from neutrons generated in the Ti chips. Summaries of our experiments are described in Section II, as is a theoretical effort based on cosmic ray muons to describe low-level neutron production. Details of the experimental groups' work are contained in the six appendices. At LLNL, independent teams were spontaneously formed in response to the early announcements on cold fusion. This report's format follows this organization.

  12. Joint FAM/Line Management Assessment Report on LLNL Machine Guarding Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, J. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-07-19

    The LLNL Safety Program for Machine Guarding is implemented to comply with requirements in the ES&H Manual Document 11.2, "Hazards-General and Miscellaneous," Section 13 Machine Guarding (Rev 18, issued Dec. 15, 2015). The primary goal of this LLNL Safety Program is to ensure that LLNL operations involving machine guarding are managed so that workers, equipment and government property are adequately protected. This means that all such operations are planned and approved using the Integrated Safety Management System to provide the most cost effective and safest means available to support the LLNL mission.

  13. Minimization and recycling of construction and demolition wastes; Minimizacion y reciclado de los residuos de construccion y demolicion (RCD)

    Energy Technology Data Exchange (ETDEWEB)

    Huete, R.; Lopez, J.A.; Ponce, M.; Llatas, C.

    1998-12-01

    We all know the damage to the environmental caused by the illegal dumping demolition waste, that causes a bad image of our cities. This damage, grows thanks to the inadequate governmental management and for the small co-operation of the owners of the wastes and we may quantify it with the necessary pressure and their impact on the environment has different aspects that should be remembered: on the economic media and on the culture. Following the recommendations of the European Union, we should place three different policies: prevention, recovery and sanitary landfilling. (Author)

  14. Characterization, minimization and disposal of radioactive, hazardous, and mixed wastes during cleanup and rransition of the Tritium Research Laboratory (TRL) at Sandia National Laboratories/California (SNL/CA)

    International Nuclear Information System (INIS)

    Garcia, T.B.; Gorman, T.P.

    1996-12-01

    This document provides an outline of waste handling practices used during the Sandia National Laboratory/California (SNL/CA), Tritium Research Laboratory (TRL) Cleanup and Transition project. Here we provide background information concerning the history of the TRL and the types of operations that generated the waste. Listed are applicable SNL/CA site-wide and TRL local waste handling related procedures. We describe personnel training practices and outline methods of handling and disposal of compactible and non-compactible low level waste, solidified waste water, hazardous wastes and mixed wastes. Waste minimization, reapplication and recycling practices are discussed. Finally, we provide a description of the process followed to remove the highly contaminated decontamination systems. This document is intended as both a historical record and as a reference to other facilities who may be involved in similar work

  15. Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1996-01-01

    A Depleted Uranium Silicate Container Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill the void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (a) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (b) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments

  16. PERAN SIKAP DALAM MEMEDIASI PENGARUH PENGETAHUAN TERHADAP PERILAKU MINIMISASI SAMPAH PADA MASYARAKAT TERBAN, YOGYAKARTA (The Role of Attitude to Mediate The Effect of Knowledge on People’s Waste Minimization Behaviour in Terban, Yogyakarta

    Directory of Open Access Journals (Sweden)

    Hanif Akhtar

    2015-01-01

    behaviour. Attitude toward behaviour plays a significant role in behavioural change. This research will focus on one kind of pro-environmental behaviour namely waste minimisastion behaviour. The purpose of this research is to find out the relationship between waste minimization knowledge, attitude, and behaviour. This research was conducted in Kelurahan Terban, RW 02 and RW 11, Yogyakarta in January until February 2014. Total of the subjects are 105. Data were collected using three scales that is: waste minimization behaviour scale, waste minimization attitude scale, and waste minimization knowledge scale. Data were analysed using regression analysis with path analysis model. Sobel Test was used to estimate the mediation effect. Indirect effect analysis showed the indirect effect coeficient was 0,742 with z=3,42 and p <0,01. It is showed that there was an indirect effect of waste minimization knowledge to waste minimization behaviour through waste minimization attitude. Thus, we can conclude that waste minimization attitude mediates the relationship between waste minimization knowledge and waste minimization behaviour.

  17. Normalized Tritium Quantification Approach (NoTQA) a Method for Quantifying Tritium Contaminated Trash and Debris at LLNL

    International Nuclear Information System (INIS)

    Dominick, J.L.; Rasmussen, C.L.

    2008-01-01

    Several facilities and many projects at LLNL work exclusively with tritium. These operations have the potential to generate large quantities of Low-Level Radioactive Waste (LLW) with the same or similar radiological characteristics. A standardized documented approach to characterizing these waste materials for disposal as radioactive waste will enhance the ability of the Laboratory to manage them in an efficient and timely manner while ensuring compliance with all applicable regulatory requirements. This standardized characterization approach couples documented process knowledge with analytical verification and is very conservative, overestimating the radioactivity concentration of the waste. The characterization approach documented here is the Normalized Tritium Quantification Approach (NoTQA). This document will serve as a Technical Basis Document which can be referenced in radioactive waste characterization documentation packages such as the Information Gathering Document. In general, radiological characterization of waste consists of both developing an isotopic breakdown (distribution) of radionuclides contaminating the waste and using an appropriate method to quantify the radionuclides in the waste. Characterization approaches require varying degrees of rigor depending upon the radionuclides contaminating the waste and the concentration of the radionuclide contaminants as related to regulatory thresholds. Generally, as activity levels in the waste approach a regulatory or disposal facility threshold the degree of required precision and accuracy, and therefore the level of rigor, increases. In the case of tritium, thresholds of concern for control, contamination, transportation, and waste acceptance are relatively high. Due to the benign nature of tritium and the resulting higher regulatory thresholds, this less rigorous yet conservative characterization approach is appropriate. The scope of this document is to define an appropriate and acceptable

  18. Controlled Landfill Project in Yolo County, California for Environmental Benefits of Waste Stabilization and Minimization of Greenhouse Gas Emissions

    Science.gov (United States)

    Yazdani, R.; Augenstein, D.; Kieffer, J.; Cohen, K.

    2003-12-01

    The Department of Public Works of Yolo County, California, USA has been testing an advanced approach to landfill bioreactors, controlled (or "enhanced") landfilling, at its Yolo County Central Landfill site near Davis, CA, since 1994. Overall objectives have been the management of waste landfilling for: (1) rapid completion of total gas generation; (2) maximum, high-efficiency gas capture; (3) waste volume reduction; and (4) maximum greenhouse gas and carbon sequestration benefits. Methane generation is controlled and enhanced through carefully managed moisture additions, and by taking advantage of landfill temperature elevation. The generated landfill methane, an important greenhouse gas, is recovered with high efficiency through extraction from a porous recovery layer beneath a surface geomembrane cover. Instrumentation included a total of 56 moisture and 15 temperature sensors in the two cells, gas flow monitoring by positive displacement gas meters, and accurate quantification of liquid inputs and outputs. Gas composition, waste volume reduction, base hydrostatic head, and a range of environmental compliance parameters has been monitored since 1995. Partitioning gas tracer tests using the injection of two gases at dilute concentrations in the landfill have also been initiated to compute the fraction of pore space occupied by water between the points of tracer injection and tracer measurement. There has been rapid waste volume reduction in the enhanced cell that corresponds to the solids' reduction to gas. Monitoring is planned for the next several years, until stabilization parameters are determined complete. Encouraging performance is indicated by: (1) sensor data; (2) gas generation results; (3) data from landfill cores; and (4) decomposition-related indicators including rapid volume reduction. When data are synthesized, project results have attractive implications for new approaches to landfill management. Over seven-years, methane recoveries have averaged

  19. OMICRON, LLNL ENDL Charged Particle Data Library Processing

    International Nuclear Information System (INIS)

    Mengoni, A.; Panini, G.C.

    2002-01-01

    1 - Description of program or function: The program has been designed to read the Evaluated Charged Particle Library (ECPL) of the LLNL Evaluated Nuclear Data Library (ENDL) and generate output in various forms: interpreted listing, ENDF format and graphs. 2 - Method of solution: A file containing ECPL in card image transmittal format is scanned to retrieve the requested reactions from the requested materials; in addition selections can be made by data type or incident particle. 3 - Restrictions on the complexity of the problem: The Reaction Property Designator I determines the type of data in the ENDL library (e.g. cross sections, angular distributions, Maxwellian averages, etc.); the program does not take into account the data for I=3,4 (energy-angle-distributions) since there are no data in the current ECPL version

  20. Release isentrope measurements with the LLNL electric gun

    Energy Technology Data Exchange (ETDEWEB)

    Gathers, G.R.; Osher, J.E.; Chau, H.H.; Weingart, R.C.; Lee, C.G.; Diaz, E.

    1987-06-01

    The liquid-vapor coexistence boundary is not well known for most metals because the extreme conditions near the critical point create severe experimental difficulties. The isentropes passing through the liquid-vapor region typically begin from rather large pressures on the Hugoniot. We are attempting to use the high velocities achievable with the Lawrence Livermore National Laboratory (LLNL) electric gun to obtain these extreme states in aluminum and measure the release isentropes by releasing into a series of calibrated standards with known Hugoniots. To achieve large pressure drops needed to explore the liquid-vapor region, we use argon gas for which Hugoniots have been calculated using the ACTEX code, as one of the release materials.

  1. Results of LLNL investigation of NYCT data sets

    International Nuclear Information System (INIS)

    Sale, K; Harrison, M; Guo, M; Groza, M

    2007-01-01

    Upon examination we have concluded that none of the alarms indicate the presence of a real threat. A brief history and results from our examination of the NYCT ASP occupancy data sets dated from 2007-05-14 19:11:07 to 2007-06-20 15:46:15 are presented in this letter report. When the ASP data collection campaign at NYCT was completed, rather than being shut down, the Canberra ASP annunciator box was unplugged leaving the data acquisition system running. By the time it was discovered that the ASP was still acquiring data about 15,000 occupancies had been recorded. Among these were about 500 alarms (classified by the ASP analysis system as either Threat Alarms or Suspect Alarms). At your request, these alarms have been investigated. Our conclusion is that none of the alarm data sets indicate the presence of a real threat (within statistics). The data sets (ICD1 and ICD2 files with concurrent JPEG pictures) were delivered to LLNL on a removable hard drive labeled FOUO. The contents of the data disk amounted to 53.39 GB of data requiring over two days for the standard LLNL virus checking software to scan before work could really get started. Our first step was to walk through the directory structure of the disk and create a database of occupancies. For each occupancy, the database was populated with the occupancy date and time, occupancy number, file path to the ICD1 data and the alarm ('No Alarm', 'Suspect Alarm' or 'Threat Alarm') from the ICD2 file along with some other incidental data. In an attempt to get a global understanding of what was going on, we investigated the occupancy information. The occupancy date/time and alarm type were binned into one-hour counts. These data are shown in Figures 1 and 2

  2. Minimizing waste (off-cuts using cutting stock model: The case of one dimensional cutting stock problem in wood working industry

    Directory of Open Access Journals (Sweden)

    Gbemileke A. Ogunranti

    2016-09-01

    Full Text Available Purpose: The main objective of this study is to develop a model for solving the one dimensional cutting stock problem in the wood working industry, and develop a program for its implementation. Design/methodology/approach: This study adopts the pattern oriented approach in the formulation of the cutting stock model. A pattern generation algorithm was developed and coded using Visual basic.NET language. The cutting stock model developed is a Linear Programming (LP Model constrained by numerous feasible patterns. A LP solver was integrated with the pattern generation algorithm program to develop a one - dimensional cutting stock model application named GB Cutting Stock Program. Findings and Originality/value: Applying the model to a real life optimization problem significantly reduces material waste (off-cuts and minimizes the total stock used. The result yielded about 30.7% cost savings for company-I when the total stock materials used is compared with the former cutting plan. Also, to evaluate the efficiency of the application, Case I problem was solved using two top commercial 1D-cutting stock software.  The results show that the GB program performs better when related results were compared. Research limitations/implications: This study round up the linear programming solution for the number of pattern to cut. Practical implications: From Managerial perspective, implementing optimized cutting plans increases productivity by eliminating calculating errors and drastically reducing operator mistakes. Also, financial benefits that can annually amount to millions in cost savings can be achieved through significant material waste reduction. Originality/value: This paper developed a linear programming one dimensional cutting stock model based on a pattern generation algorithm to minimize waste in the wood working industry. To implement the model, the algorithm was coded using VisualBasic.net and linear programming solver called lpsolvedll (dynamic

  3. Evaluation of a modified Zirflex process to minimize high-level waste generation at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Chipman, N.A.; Carleson, T.E.

    1987-06-01

    Extensive laboratory experimentation was conducted to develop a dissolvent suitable for Zircaloy based fuels having a surface oxide coating. Other laboratory experimentation was conducted on the precipitation and solids separation steps of the process. Computer simulation was used to determine the stability and uranium extractability of the output stream, and potential waste volume reduction. From these studies a conceptual flowsheet was developed which could potentially reduce HLW volumes by about 30%. Other process alternatives being investigated achieve equal HLW volume reduction and potentially improve safety of operation. Therefore, the Modified Zirflex process is not presently being considered for further development. 22 refs., 21 figs., 3 tabs

  4. Evaluation of LLNL BSL-3 Maximum Credible Event Potential Consequence to the General Population and Surrounding Environment

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2010-08-16

    The purpose of this evaluation is to establish reproducibility of the analysis and consequence results to the general population and surrounding environment in the LLNL Biosafety Level 3 Facility Environmental Assessment (LLNL 2008).

  5. Use of Novel Highly Selective Ion Exchange Media for Minimizing the Waste Arising from Different NPP and Other Liquids

    International Nuclear Information System (INIS)

    Tusa, Esko; Harjula, Risto; Lehto, Jukka

    2003-01-01

    Highly selective inorganic ion exchangers give new possibilities to implement and operate new innovative treatment systems for radioactive liquids. Because of high selectivity these ion exchangers can be used even in liquids of high salt concentrations. Only selected target nuclides will be separated and inactive salts are left in the liquid, which can be released or recategorized. Thus, it is possible to reduce the volume of radioactive waste dramatically. On the other hand, only a small volume of highly selective material is required in applications, which makes it possible to design totally new types of compact treatment systems. The major benefit of selective ion exchange media comes from the very large volume reduction of radioactive waste in final disposal. It is also possible to save in investment costs, because small ion exchanger volumes can be used and handled in a very small facility. This paper describes different applications of these highly selective ion exchangers, both commercial fullscale applications and laboratory tests, to give the idea of their efficiency for different liquids

  6. 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

  7. Implementation of flowsheet change to minimize hydrogen and ammonia generation during chemical processing of high level waste in the Defense Waste Processing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, Dan P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Woodham, Wesley H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, Matthew S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Newell, J. David [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Luther, Michelle C. [Auburn Univ., AL (United States); Brandenburg, Clayton H. [Univ.of South Carolina, Columbia, SC (United States)

    2016-09-27

    Testing was completed to develop a chemical processing flowsheet for the Defense Waste Processing Facility (DWPF), designed to vitrify and stabilize high level radioactive waste. DWPF processing uses a reducing acid (formic acid) and an oxidizing acid (nitric acid) to rheologically thin the slurry and complete the necessary acid base and reduction reactions (primarily mercury and manganese). Formic acid reduces mercuric oxide to elemental mercury, allowing the mercury to be removed during the boiling phase of processing through steam stripping. In runs with active catalysts, formic acid can decompose to hydrogen and nitrate can be reduced to ammonia, both flammable gases, due to rhodium and ruthenium catalysis. Replacement of formic acid with glycolic acid eliminates the generation of rhodium- and ruthenium-catalyzed hydrogen and ammonia. In addition, mercury reduction is still effective with glycolic acid. Hydrogen, ammonia and mercury are discussed in the body of the report. Ten abbreviated tests were completed to develop the operating window for implementation of the flowsheet and determine the impact of changes in acid stoichiometry and the blend of nitric and glycolic acid as it impacts various processing variables over a wide processing region. Three full-length 4-L lab-scale simulations demonstrated the viability of the flowsheet under planned operating conditions. The flowsheet is planned for implementation in early 2017.

  8. Strategies to enhance waste minimization and energy conservation within organizations: a case study from the UK construction sector.

    Science.gov (United States)

    Jones, Jo; Jackson, Janet; Tudor, Terry; Bates, Margaret

    2012-09-01

    Strategies for enhancing environmental management are a key focus for the government in the UK. Using a manufacturing company from the construction sector as a case study, this paper evaluates selected interventionist techniques, including environmental teams, awareness raising and staff training to improve environmental performance. The study employed a range of methods including questionnaire surveys and audits of energy consumption and generation of waste to examine the outcomes of the selected techniques. The results suggest that initially environmental management was not a focus for either the employees or the company. However, as a result of employing the techniques, the company was able to reduce energy consumption, increase recycling rates and achieve costs savings in excess of £132,000.

  9. Summary Statistics for Homemade ?Play Dough? -- Data Acquired at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Kallman, J S; Morales, K E; Whipple, R E; Huber, R D; Martz, A; Brown, W D; Smith, J A; Schneberk, D J; Martz, Jr., H E; White, III, W T

    2010-03-11

    Using x-ray computerized tomography (CT), we have characterized the x-ray linear attenuation coefficients (LAC) of a homemade Play Dough{trademark}-like material, designated as PDA. Table 1 gives the first-order statistics for each of four CT measurements, estimated with a Gaussian kernel density estimator (KDE) analysis. The mean values of the LAC range from a high of about 2700 LMHU{sub D} 100kVp to a low of about 1200 LMHUD at 300kVp. The standard deviation of each measurement is around 10% to 15% of the mean. The entropy covers the range from 6.0 to 7.4. Ordinarily, we would model the LAC of the material and compare the modeled values to the measured values. In this case, however, we did not have the detailed chemical composition of the material and therefore did not model the LAC. Using a method recently proposed by Lawrence Livermore National Laboratory (LLNL), we estimate the value of the effective atomic number, Z{sub eff}, to be near 10. LLNL prepared about 50mL of the homemade 'Play Dough' in a polypropylene vial and firmly compressed it immediately prior to the x-ray measurements. We used the computer program IMGREC to reconstruct the CT images. The values of the key parameters used in the data capture and image reconstruction are given in this report. Additional details may be found in the experimental SOP and a separate document. To characterize the statistical distribution of LAC values in each CT image, we first isolated an 80% central-core segment of volume elements ('voxels') lying completely within the specimen, away from the walls of the polypropylene vial. All of the voxels within this central core, including those comprised of voids and inclusions, are included in the statistics. We then calculated the mean value, standard deviation and entropy for (a) the four image segments and for (b) their digital gradient images. (A digital gradient image of a given image was obtained by taking the absolute value of the difference

  10. Criticality Safety Support to a Project Addressing SNM Legacy Items at LLNL

    International Nuclear Information System (INIS)

    Pearson, J S; Burch, J G; Dodson, K E; Huang, S T

    2005-01-01

    and new ES and H container labels applied. In many cases, legacy material that was inspected was determined to be excess to programmatic needs and it was then either processed to meet the DOE-3013-STD or designated as TRU waste and disposed of accordingly. During FY2003 through FY2004 approximately 1600 items were opened and the items processed if necessary, repackaged and newly labeled with ES and H labels. As of April, 2005, there are only 32 non-ES and H labeled items in existence within the Plutonium Facility. Due to a consolidated effort in dealing with the legacy items, the problems associated with storage of these items at LLNL has been substantially abated. The paper will discuss the background, implementation, and results of the SNM Legacy Items Implementation Project. Benefits and Lessons Learned will be identified

  11. Estimating The Reliability of the Lawrence Livermore National Laboratory (LLNL) Flash X-ray (FXR) Machine

    International Nuclear Information System (INIS)

    Ong, M M; Kihara, R; Zentler, J M; Kreitzer, B R; DeHope, W J

    2007-01-01

    At Lawrence Livermore National Laboratory (LLNL), our flash X-ray accelerator (FXR) is used on multi-million dollar hydrodynamic experiments. Because of the importance of the radiographs, FXR must be ultra-reliable. Flash linear accelerators that can generate a 3 kA beam at 18 MeV are very complex. They have thousands, if not millions, of critical components that could prevent the machine from performing correctly. For the last five years, we have quantified and are tracking component failures. From this data, we have determined that the reliability of the high-voltage gas-switches that initiate the pulses, which drive the accelerator cells, dominates the statistics. The failure mode is a single-switch pre-fire that reduces the energy of the beam and degrades the X-ray spot-size. The unfortunate result is a lower resolution radiograph. FXR is a production machine that allows only a modest number of pulses for testing. Therefore, reliability switch testing that requires thousands of shots is performed on our test stand. Study of representative switches has produced pre-fire statistical information and probability distribution curves. This information is applied to FXR to develop test procedures and determine individual switch reliability using a minimal number of accelerator pulses

  12. LLNL medical and industrial laser isotope separation: large volume, low cost production through advanced laser technologies

    International Nuclear Information System (INIS)

    Comaskey, B.; Scheibner, K. F.; Shaw, M.; Wilder, J.

    1998-01-01

    The goal of this LDRD project was to demonstrate the technical and economical feasibility of applying laser isotope separation technology to the commercial enrichment (>lkg/y) of stable isotopes. A successful demonstration would well position the laboratory to make a credible case for the creation of an ongoing medical and industrial isotope production and development program at LLNL. Such a program would establish LLNL as a center for advanced medical isotope production, successfully leveraging previous LLNL Research and Development hardware, facilities, and knowledge

  13. Test results from the LLNL 250 GHz CARM experiment

    International Nuclear Information System (INIS)

    Kulke, B.; Caplan, M.; Bubp, D.; Houck, T.; Rogers, D.; Trimble, D.; VanMaren, R.; Westenskow, G.; McDermott, D.B.; Luhmann, N.C. Jr.; Danly, B.

    1991-01-01

    The authors have completed the initial phase of a 250 GHz CARM experiment, driven by the 2 MeV, 1 kA, 30 ns induction linac at the LLNL ARC facility. A non-Brillouin, solid, electron beam is generated from a flux-threaded, thermionic cathode. As the beam traverses a 10 kG plateau produced by a superconducting magnet, ten percent of the beam energy is converted into rotational energy in a bifilar helix wiggler that produces a spiraling, 50 G, transverse magnetic field. The beam is then compressed to a 5 mm diameter as it drifts into a 30 kG plateau. For the present experiment, the CARM interaction region consisted of a single Bragg section resonator, followed by a smooth-bore amplifier section. Using high-pass filters, they have observed broadband output signals estimated to be at the several megawatt level in the range 140 to over 230 GHz. This is consistent with operation as a superradiant amplifier. Simultaneously, they also observed K a band power levels near 3 MW

  14. Test results from the LLNL 250 GHz CARM experiment

    International Nuclear Information System (INIS)

    Kulke, B.; Caplan, M.; Bubp, D.; Houck, T.; Rogers, D.; Trimble, D.; VanMaren, R.; Westenskow, G.; McDermott, D.B.; Luhmann, N.C. Jr.; Danly, B.

    1991-05-01

    We have completed the initial phase of a 250 GHz CARM experiment, driven by the 2 MeV, 1 kA, 30 ns induction linac at the LLNL ARC facility. A non-Brillouin, solid, electron beam is generated from a flux-threaded, thermionic cathode. As the beam traverses a 10 kG plateau produced by a superconducting magnet, ten percent of the beam energy is converted into rotational energy in a bifilar helix wiggler that produces a spiraling, 50 G, transverse magnetic field. The beam is then compressed to a 5 mm diameter as it drifts into a 30 kG plateau. For the present experiment, the CARM interaction region consisted of a single Bragg section resonator, followed by a smooth-bore amplifier section. Using high-pass filters, we have observed broadband output signals estimated to be at the several megawatt level in the range 140 to over 230 GHz. This is consistent with operation as a superradiant amplifier. Simultaneously, we also observed K a band power levels near 3 MW

  15. Net Weight Issue LLNL DOE-STD-3013 Containers

    International Nuclear Information System (INIS)

    Wilk, P

    2008-01-01

    The following position paper will describe DOE-STD-3013 container sets No.L000072 and No.L000076, and how they are compliant with DOE-STD-3013-2004. All masses of accountable nuclear materials are measured on LLNL certified balances maintained under an MC and A Program approved by DOE/NNSA LSO. All accountability balances are recalibrated annually and checked to be within calibration on each day that the balance is used for accountability purposes. A statistical analysis of the historical calibration checks from the last seven years indicates that the full-range Limit of Error (LoE, 95% confidence level) for the balance used to measure the mass of the contents of the above indicated 3013 containers is 0.185 g. If this error envelope, at the 95% confidence level, were to be used to generate an upper-limit to the measured weight of the containers No.L000072 and No.L000076, the error-envelope would extend beyond the 5.0 kg 3013-standard limit on the package contents by less than 0.3 g. However, this is still well within the intended safety bounds of DOE-STD-3013-2004

  16. Waste minimization opportunities at the U.S. Uranium Mill Tailings Remedial Action (UMTRA) Project, Rifle, Colorado, site

    International Nuclear Information System (INIS)

    Hartmann, G.L.; Arp, S.; Hempill, H.

    1993-01-01

    At two uranium mill sites in Rifle, Colorado, the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is removing uranium mill tailings and contaminated subgrade soils. This remediation activity will result in the production of groundwater contaminated with uranium, heavy metals, ammonia, sulfates, and total dissolved solids (TDS). The initial remediation plan called for a wastewater treatment plant for removal of the uranium, heavy metals, and ammonia, with disposal of the treated water, which still includes the sulfates and TDSS, to the Colorado River. The National Pollutant Discharge Elimination (NPDES) permit issued by the Colorado Department of Health for the two Rifle sites contained more restrictive discharge limits than originally anticipated. During the detailed review of alternate treatment systems to meet these more restrictive limits, the proposed construction procedures were reviewed emphasizing the methods to minimize groundwater production to reduce the size of the water treatment facility, or to eliminate it entirely. It was determined that with changes to the excavation procedures and use of the contaminated groundwater for use in dust suppression at the disposal site, discharge to the river could be eliminated completely

  17. High exhaust chrome complex using chrome tanned tannery, solid wastes and common hydrocarbons as reductants and masking agents to minimize the liquid and solid wastes: tanning and environmental impact studies

    International Nuclear Information System (INIS)

    Nawaz, H.R.

    2005-01-01

    Still no alternate of chrome tanning has been found to achieve the best quality and quantity of leather. But the chrome tanning process is associated with the generation of very toxic liquid and solid wastes. Therefore we emphasized to develop an efficient process for the synthesis of high exhaust chrome complex that could minimize the both liquid and solid wastes up to very low limit. In this research, chrome shavings and raw organic compounds have beneficially utilized as a reductant as well as potential masking agents providing a comprehensive close loop. Two chrome tanning materials have been developed using leather shavings with molasses in product A and replacement of molasses by other organic compounds for chrome complex B. These materials have also been employed for the tanning of goatskins parallel to the commercial BCS from the market. The comparative studies revealed that, the quality of leather made from product B is either better or comparable with the conventional tanning material. The chrome contents in leather have been increased with the simultaneous decreased in spent chrome liquor. Hence the exhaustion rate of chrome complex B has been noted up to 95%. While the physical characteristics of resulted leather from product A and B have been found comparable to that of conventional tanned leather. Therefore this methodology would not only reduce liquid and solid wastes but also provide quality leather and economically multi benefits. (author)

  18. Applying interactive control to waste processing operations

    International Nuclear Information System (INIS)

    Grasz, E.L.; Merrill, R.D.; Couture, S.A.

    1992-08-01

    At present waste and residue processing includes steps that require human interaction. The risk of exposure to unknown hazardous materials and the potential for radiation contamination motivates the desire to remove operators from these processes. Technologies that facilitate this include glove box robotics, modular systems for remote and automated servicing, and interactive controls that minimize human intervention. LLNL is developing an automated system which is designed to supplant the operator for glove box tasks, thus protecting the operator from the risk of radiation exposure and minimizing operator-associated waste. Although most of the processing can be automated with minimal human interaction, there are some tasks where intelligent intervention is both desirable and necessary to adapt to Enexpected circumstances and events. These activities require that the operator interact with the process using a remote manipulator which provides or reflects a natural feel to the operator. The remote manipulation system which was developed incorporates sensor fusion and interactive control, and provides the operator with an effective means of controlling the robot in a potentially unknown environment. This paper describes recent accomplishments in technology development and integration, and outlines the future goals of Lawrence Livermore National Laboratory for achieving this integrated interactive control capability

  19. Training the Masses ? Web-based Laser Safety Training at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Sprague, D D

    2004-12-17

    The LLNL work smart standard requires us to provide ongoing laser safety training for a large number of persons on a three-year cycle. In order to meet the standard, it was necessary to find a cost and performance effective method to perform this training. This paper discusses the scope of the training problem, specific LLNL training needs, various training methods used at LLNL, the advantages and disadvantages of these methods and the rationale for selecting web-based laser safety training. The tools and costs involved in developing web-based training courses are also discussed, in addition to conclusions drawn from our training operating experience. The ILSC lecture presentation contains a short demonstration of the LLNL web-based laser safety-training course.

  20. Proposals for ORNL [Oak Ridge National Laboratory] support to Tiber LLNL [Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Berry, L.A.; Rosenthal, M.W.; Saltmarsh, M.J.; Shannon, T.E.; Sheffield, J.

    1987-01-01

    This document describes the interests and capabilities of Oak Ridge National Laboratory in their proposals to support the Lawrence Livermore National Laboratory (LLNL) Engineering Test Reactor (ETR) project. Five individual proposals are cataloged separately. (FI)

  1. LLNL Center of Excellence Work Items for Q9-Q10 period

    Energy Technology Data Exchange (ETDEWEB)

    Neely, J. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-09-02

    This work plan encompasses a slice of effort going on within the ASC program, and for projects utilizing COE vendor resources, describes work that will be performed by both LLNL staff and COE vendor staff collaboratively.

  2. The National Ignition Facility (NIF) and High Energy Density Science Research at LLNL (Briefing Charts)

    Science.gov (United States)

    2013-06-21

    The National Ignition Facility ( NIF ) and High Energy Density Science Research at LLNL Presentation to: IEEE Pulsed Power and Plasma Science...Conference C. J. Keane Director, NIF User Office June 21, 2013 1491978-1-4673-5168-3/13/$31.00 ©2013 IEEE Report Documentation Page Form ApprovedOMB No...4. TITLE AND SUBTITLE The National Ignition Facility ( NIF ) and High Energy Density Science Research at LLNL 5a. CONTRACT NUMBER 5b. GRANT

  3. Linear collider research and development at SLAC, LBL and LLNL

    International Nuclear Information System (INIS)

    Mattison, T.S.

    1988-10-01

    The study of electron-positron (e + e/sup /minus//) annihilation in storage ring colliders has been very fruitful. It is by now well understood that the optimized cost and size of e + e/sup /minus// storage rings scales as E(sub cm//sup 2/ due to the need to replace energy lost to synchrotron radiation in the ring bending magnets. Linear colliders, using the beams from linear accelerators, evade this scaling law. The study of e/sup +/e/sup /minus// collisions at TeV energy will require linear colliders. The luminosity requirements for a TeV linear collider are set by the physics. Advanced accelerator research and development at SLAC is focused toward a TeV Linear Collider (TLC) of 0.5--1 TeV in the center of mass, with a luminosity of 10/sup 33/--10/sup 34/. The goal is a design for two linacs of less than 3 km each, and requiring less than 100 MW of power each. With a 1 km final focus, the TLC could be fit on Stanford University land (although not entirely within the present SLAC site). The emphasis is on technologies feasible for a proposal to be framed in 1992. Linear collider development work is progressing on three fronts: delivering electrical energy to a beam, delivering a focused high quality beam, and system optimization. Sources of high peak microwave radio frequency (RF) power to drive the high gradient linacs are being developed in collaboration with Lawrence Berkeley Laboratory (LBL) and Lawrence Livermore National Laboratory (LLNL). Beam generation, beam dynamics and final focus work has been done at SLAC and in collaboration with KEK. Both the accelerator physics and the utilization of TeV linear colliders were topics at the 1988 Snowmass Summer Study. 14 refs., 4 figs., 1 tab

  4. Progress in AMS measurements at the LLNL spectrometer

    International Nuclear Information System (INIS)

    Southon, J.R.; Vogel, J.S.; Trumbore, S.E.; Davis, J.C.; Roberts, M.L.; Caffee, M.; Finkel, R.; Proctor, I.D.; Heikkinen, D.W.; Berno, A.J.; Hornady, R.S.

    1991-06-01

    The AMS measurement program at LLNL began in earnest in late 1989, and has initially concentrated on 14 C measurements for biomedical and geoscience applications. We have now begun measurements on 10 Be and 36 Cl, are presently testing the spectrometer performance for 26 Al and 3 H, and will begin tests on 7 Be, 41 Ca and 129 I within the next few months. Our laboratory has a strong biomedical AMS program of 14 C tracer measurements involving large numbers of samples (sometimes hundreds in a single experiment) at 14 C concentrations which are typically .5--5 times Modern, but are occasionally highly enriched. The sample preparation techniques required for high throughput and low cross-contamination for this work are discussed elsewhere. Similar demands are placed on the AMS measurement system, and in particular on the ion source. Modifications to our GIC 846 ion source, described below, allow us to run biomedical and geoscience or archaeological samples in the same source wheel with no adverse effects. The source has a capacity for 60 samples (about 45 unknown) in a single wheel and provides currents of 30--60μA of C - from hydrogen-reduced graphite. These currents and sample capacity provide high throughput for both biomedical and other measurements: the AMS system can be started up, tuned, and a wheel of carbon samples measured to 1--1.5% in under a day; and 2 biomedical wheels can be measured per day without difficulty. We report on the present status of the Lawrence Livermore AMS spectrometer, including sample throughput and progress towards routine 1% measurement capability for 14 C, first results on other isotopes, and experience with a multi-sample high intensity ion source. 5 refs

  5. Challenges in biotechnology at LLNL: from genes to proteins; TOPICAL

    International Nuclear Information System (INIS)

    Albala, J S

    1999-01-01

    This effort has undertaken the task of developing a link between the genomics, DNA repair and structural biology efforts within the Biology and Biotechnology Research Program at LLNL. Through the advent of the I.M.A.G.E. (Integrated Molecular Analysis of Genomes and their Expression) Consortium, a world-wide effort to catalog the largest public collection of genes, accepted and maintained within BBRP, it is now possible to systematically express the protein complement of these to further elucidate novel gene function and structure. The work has ensued in four phases, outlined as follows: (1) Gene and System selection; (2) Protein expression and purification; (3) Structural analysis; and (4) biological integration. Proteins to be expressed have been those of high programmatic interest. This includes, in particular, proteins involved in the maintenance of genome integrity, particularly those involved in the repair of DNA damage, including ERCC1, ERCC4, XRCC2, XRCC3, XRCC9, HEX1, APN1, p53, RAD51B, RAD51C, and RAD51. Full-length cDNA cognates of selected genes were isolated, and cloned into baculovirus-based expression vectors. The baculoviral expression system for protein over-expression is now well-established in the Albala laboratory. Procedures have been successfully optimized for full-length cDNA clining into expression vectors for protein expression from recombinant constructs. This includes the reagents, cell lines, techniques necessary for expression of recombinant baculoviral constructs in Spodoptera frugiperda (Sf9) cells. The laboratory has also generated a high-throughput baculoviral expression paradigm for large scale expression and purification of human recombinant proteins amenable to automation

  6. Waste management

    International Nuclear Information System (INIS)

    Chmielewska, E.

    2010-01-01

    In this chapter formation of wastes and basic concepts of non-radioactive waste management are explained. This chapter consists of the following parts: People in Peril; Self-regulation of nature as a guide for minimizing and recycling waste; The current waste management situation in the Slovak Republic; Categorization and determination of the type of waste in legislative of Slovakia; Strategic directions waste management in the Slovak Republic.

  7. Waste minimization concepts applied to oil spill response or (integrating the Pollution Prevention Act of 1990 with the Oil Pollution Act of 1990)

    International Nuclear Information System (INIS)

    Ferriere, D.V.

    1993-01-01

    As of July 23, 1993 the National Contingency Plan (NCP) for oil spills and hazardous substance releases (40CFR300) is being revised to comply with Oil Pollution Act 1990 (OPA '90) requirements. An important OPA '90 development is the creation of localized groups to write Area Contingency Plans (ACPs). During the ACP process many political, economical, and environmental issues will be addressed by representatives from several local, county, state, federal agencies and industry. Some of the difficulty decision makers must face is weighing environmental tradeoffs considering socio-economic aspects and determining what is the most effective ecologically sensible/environmental protection oil spill response strategy. Ideally, the NCP is designed as a democratic process providing a voice to all effected parties on how to best protect the environment, natural resources, and commercial resources. However, practice has shown successful emergency response is best handled when a single focal point of command, commonly referred to as incident command, has an agreed upon response agenda. The following will address the need for decision makers and contingency planners to at least address waste minimization principles, if not make it their primary focus, when developing and executing the oil spill response plan

  8. Retention-tank systems: A unique operating practice for managing complex waste streams at research and development facilities

    International Nuclear Information System (INIS)

    Brigdon, S.

    1996-01-01

    The importance of preventing the introduction of prohibited contaminants to the sanitary sewer is critical to the management of large federal facilities such as the Lawrence Livermore National Laboratory (LLNL). LLNL operates 45 retention-tank systems to control wastewater discharges and to maintain continued compliance with environmental regulations. LLNL's unique internal operation practices successfully keep prohibited contaminants out of the sanitary waste stream and maintain compliance with federal, state, and local regulations, as well as determining appropriate wastewater-disposal options. Components of the system include sampling and analysis of the waste stream, evaluation of the data, discharge approval, and final disposition of the waste stream

  9. Minimal surfaces

    CERN Document Server

    Dierkes, Ulrich; Sauvigny, Friedrich; Jakob, Ruben; Kuster, Albrecht

    2010-01-01

    Minimal Surfaces is the first volume of a three volume treatise on minimal surfaces (Grundlehren Nr. 339-341). Each volume can be read and studied independently of the others. The central theme is boundary value problems for minimal surfaces. The treatise is a substantially revised and extended version of the monograph Minimal Surfaces I, II (Grundlehren Nr. 295 & 296). The first volume begins with an exposition of basic ideas of the theory of surfaces in three-dimensional Euclidean space, followed by an introduction of minimal surfaces as stationary points of area, or equivalently

  10. Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010

    International Nuclear Information System (INIS)

    Hickman, D.P.; Wysong, A.R.; Heinrichs, D.P.; Wong, C.T.; Merritt, M.J.; Topper, J.D.; Gressmann, F.A.; Madden, D.J.

    2011-01-01

    The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE

  11. Operating characteristics and modeling of the LLNL 100-kV electric gun

    International Nuclear Information System (INIS)

    Osher, J.E.; Barnes, G.; Chau, H.H.; Lee, R.S.; Lee, C.; Speer, R.; Weingart, R.C.

    1989-01-01

    In the electric gun, the explosion of an electrically heated metal foil and the accompanying magnetic forces drive a thin flyer plate up a short barrel. Flyer velocities of up to 18 km/s make the gun useful for hypervelocity impact studies. The authors briefly review the technological evolution of the exploding-metal circuit elements that power the gun, describe the 100-kV electric gun designed at Lawrence Livermore National Laboratory (LLNL) in some detail, and present the general principles of electric gun operation. They compare the experimental performance of the LLNL gun with a simple model and with predictions of a magnetohydrodynamics code

  12. Comprehensive Angular Response Study of LLNL Panasonic Dosimeter Configurations and Artificial Intelligence Algorithm

    Energy Technology Data Exchange (ETDEWEB)

    Stone, D. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-06-30

    In April of 2016, the Lawrence Livermore National Laboratory External Dosimetry Program underwent a Department of Energy Laboratory Accreditation Program (DOELAP) on-site assessment. The assessment reported a concern that the study performed in 2013 Angular Dependence Study Panasonic UD-802 and UD-810 Dosimeters LLNL Artificial Intelligence Algorithm was incomplete. Only the responses at ±60° and 0° were evaluated and independent data from dosimeters was not used to evaluate the algorithm. Additionally, other configurations of LLNL dosimeters were not considered in this study. This includes nuclear accident dosimeters (NAD) which are placed in the wells surrounding the TLD in the dosimeter holder.

  13. Mixed waste study, Lawrence Livermore National Laboratory Hazardous Waste Management facilities

    International Nuclear Information System (INIS)

    1990-11-01

    This document addresses the generation and storage of mixed waste at Lawrence Livermore National Laboratory (LLNL) from 1984 to 1990. Additionally, an estimate of remaining storage capacity based on the current inventory of low-level mixed waste and an approximation of current generation rates is provided. Section 2 of this study presents a narrative description of Environmental Protection Agency (EPA) and Department of Energy (DOE) requirements as they apply to mixed waste in storage at LLNL's Hazardous Waste Management (HWM) facilities. Based on information collected from the HWM non-TRU radioactive waste database, Section 3 presents a data consolidation -- by year of storage, location, LLNL generator, EPA code, and DHS code -- of the quantities of low-level mixed waste in storage. Related figures provide the distribution of mixed waste according to each of these variables. A historical review follows in Section 4. The trends in type and quantity of mixed waste managed by HWM during the past five years are delineated and graphically illustrated. Section 5 provides an estimate of remaining low-level mixed waste storage capacity at HWM. The estimate of remaining mixed waste storage capacity is based on operational storage capacity of HWM facilities and the volume of all waste currently in storage. An estimate of the time remaining to reach maximum storage capacity is based on waste generation rates inferred from the HWM database and recent HWM documents. 14 refs., 18 figs., 9 tabs

  14. MINIMASI RESIKO DALAM SISTEM PENGELOLAAN LIMBAH MEDIS DI KOTA BANDUNG, INDONESIA DENGAN PENDEKATAN LINEAR PROGRAMMING (Risk Minimization for Medical Waste Management System in Bandung City, Indonesia: A Linear Programming Approach

    Directory of Open Access Journals (Sweden)

    Mochammad Chaerul

    2013-07-01

    Full Text Available ABSTRAK Berbagai macam pelayanan perawatan kesehatan yang disediakan oleh rumah sakit akan berpotensi menghasilkan limbah medis. Walaupun sebagian besar limbah rumah sakit dapat dikelompokkan sebagai limbah yang tidak berbahaya yang memiliki sifat yang sama dengan sampah rumah tangga dan dapat dibuang ke tempat penimbunan sampah, sebagian kecil dari limbah medis harus dikelola dengan tepat untuk meminimasi resiko terhadap kesehatan masyarakat. Model pengelolaan limbah medis yang dikembangkan ditujukan untuk meminimasi resiko terhadap fasilitas umum dan komersial seperti fasilitas ibadah, bank, perkantoran, restoran, hotel, stasiun pengisian bahan bakar, fasilitas pendidikan, mall dan pusat perbelanjaan, taman dan pusat olahraga/kebugaran, akibat pengangkutan limbah medis dan abu hasil pengolahannya. Tingkat resiko dari setiap fasilitas di atas ditentukan menggunakan metode Analytical Hierarchy Process (AHP. Permasalahan diselesaikan dengan mengaplikasikan linear programming menggunakan software optimimasi LINGO®. Output model berupa optimasi alokasi limbah medis dari setiap rumah sakit ke fasilitas pengolahan dan alokasi abu dari fasilitas pengolahan ke tempat penimbunan akhir. Hasil model memperlihatkan bahwa rute terpendek tidak menghasilkan total resiko terkecil karena dipengaruhi oleh jumlah dan tingkat resiko dari setiap fasilitas yang dilalui oleh kemdaraan pengangkut limbah medis dan abu. Perbedaan fasilitas yang berada di sekitar pengolahan limbah medis juga akan menghasilkan total resiko yang berbeda. ABSTRACT A broad range of healthcare services provided by hospital may generate medical waste. Although a large percentage of hospital waste is classified as general waste, which has similar nature as that of municipal solid waste and, therefore, could be disposed in municipal landfill, a small portion of medical waste has to be managed in a proper manner to minimize risk to public health. A medical waste management model is proposed in

  15. Wastes

    International Nuclear Information System (INIS)

    Bovard, Pierre

    The origin of the wastes (power stations, reprocessing, fission products) is determined and the control ensuring the innocuity with respect to man, public acceptance, availability, economics and cost are examined [fr

  16. 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.

  17. 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.

  18. Summary of the LLNL one-dimensional transport-kinetics model of the troposphere and stratosphere: 1981

    International Nuclear Information System (INIS)

    Wuebbles, D.J.

    1981-09-01

    Since the LLNL one-dimensional coupled transport and chemical kinetics model of the troposphere and stratosphere was originally developed in 1972 (Chang et al., 1974), there have been many changes to the model's representation of atmospheric physical and chemical processes. A brief description is given of the current LLNL one-dimensional coupled transport and chemical kinetics model of the troposphere and stratosphere

  19. National Uranium Resource Evaluation Program: the Hydrogeochemical Stream Sediment Reconnaissance Program at LLNL

    International Nuclear Information System (INIS)

    Higgins, G.H.

    1980-08-01

    From early 1975 to mid 1979, Lawrence Livermore National Laboratory (LLNL) participated in the Hydrogeochemical Stream Sediment Reconnaissance (HSSR), part of the National Uranium Resource Evaluation (NURE) program sponsored by the Department of Energy (DOE). The Laboratory was initially responsible for collecting, analyzing, and evaluating sediment and water samples from approximately 200,000 sites in seven western states. Eventually, however, the NURE program redefined its sampling priorities, objectives, schedules, and budgets, with the increasingly obvious result that LLNL objectives and methodologies were not compatible with those of the NURE program office, and the LLNL geochemical studies were not relevant to the program goal. The LLNL portion of the HSSR program was consequently terminated, and all work was suspended by June 1979. Of the 38,000 sites sampled, 30,000 were analyzed by instrumental neutron activation analyses (INAA), delayed neutron counting (DNC), optical emission spectroscopy (OES), and automated chloride-sulfate analyses (SC). Data from about 13,000 sites have been formally reported. From each site, analyses were published of about 30 of the 60 elements observed. Uranium mineralization has been identified at several places which were previously not recognized as potential uranium source areas, and a number of other geochemical anomalies were discovered

  20. Beam-beam studies for the proposed SLAC/LBL/LLNL B Factory

    International Nuclear Information System (INIS)

    Furman, M.A.

    1991-05-01

    We present a summary of beam-beam dynamics studies that have been carried out to date for the proposed SLAC/LBL/LLNL B Factory. Most of the material presented here is contained in the proposal's Conceptual Design Report, although post-CDR studies are also presented. 15 refs., 6 figs., 2 tabs

  1. Dispersion of Radionuclides and Exposure Assessment in Urban Environments: A Joint CEA and LLNL Report

    Energy Technology Data Exchange (ETDEWEB)

    Glascoe, Lee [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gowardhan, Akshay [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lennox, Kristin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Simpson, Matthew [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Yu, Kristen [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Armand, Patrick [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Duchenne, Christophe [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Mariotte, Frederic [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Pectorin, Xavier [Alternative Energies and Atomic Energy Commission (CEA), Paris (France)

    2014-12-19

    In the interest of promoting the international exchange of technical expertise, the US Department of Energy’s Office of Emergency Operations (NA-40) and the French Commissariat à l'Energie Atomique et aux énergies alternatives (CEA) requested that the National Atmospheric Release Advisory Center (NARAC) of Lawrence Livermore National Laboratory (LLNL) in Livermore, California host a joint table top exercise with experts in emergency management and atmospheric transport modeling. In this table top exercise, LLNL and CEA compared each other’s flow and dispersion models. The goal of the comparison is to facilitate the exchange of knowledge, capabilities, and practices, and to demonstrate the utility of modeling dispersal at different levels of computational fidelity. Two modeling approaches were examined, a regional scale modeling approach, appropriate for simple terrain and/or very large releases, and an urban scale modeling approach, appropriate for small releases in a city environment. This report is a summary of LLNL and CEA modeling efforts from this exercise. Two different types of LLNL and CEA models were employed in the analysis: urban-scale models (Aeolus CFD at LLNL/NARAC and Parallel- Micro-SWIFT-SPRAY, PMSS, at CEA) for analysis of a 5,000 Ci radiological release and Lagrangian Particle Dispersion Models (LODI at LLNL/NARAC and PSPRAY at CEA) for analysis of a much larger (500,000 Ci) regional radiological release. Two densely-populated urban locations were chosen: Chicago with its high-rise skyline and gridded street network and Paris with its more consistent, lower building height and complex unaligned street network. Each location was considered under early summer daytime and nighttime conditions. Different levels of fidelity were chosen for each scale: (1) lower fidelity mass-consistent diagnostic, intermediate fidelity Navier-Stokes RANS models, and higher fidelity Navier-Stokes LES for urban-scale analysis, and (2) lower-fidelity single

  2. Dispersion of Radionuclides and Exposure Assessment in Urban Environments: A Joint CEA and LLNL Report

    International Nuclear Information System (INIS)

    Glascoe, Lee; Gowardhan, Akshay; Lennox, Kristin; Simpson, Matthew; Yu, Kristen; Armand, Patrick; Duchenne, Christophe; Mariotte, Frederic; Pectorin, Xavier

    2014-01-01

    In the interest of promoting the international exchange of technical expertise, the US Department of Energy’s Office of Emergency Operations (NA-40) and the French Commissariat à l'Energie Atomique et aux énergies alternatives (CEA) requested that the National Atmospheric Release Advisory Center (NARAC) of Lawrence Livermore National Laboratory (LLNL) in Livermore, California host a joint table top exercise with experts in emergency management and atmospheric transport modeling. In this table top exercise, LLNL and CEA compared each other's flow and dispersion models. The goal of the comparison is to facilitate the exchange of knowledge, capabilities, and practices, and to demonstrate the utility of modeling dispersal at different levels of computational fidelity. Two modeling approaches were examined, a regional scale modeling approach, appropriate for simple terrain and/or very large releases, and an urban scale modeling approach, appropriate for small releases in a city environment. This report is a summary of LLNL and CEA modeling efforts from this exercise. Two different types of LLNL and CEA models were employed in the analysis: urban-scale models (Aeolus CFD at LLNL/NARAC and Parallel- Micro-SWIFT-SPRAY, PMSS, at CEA) for analysis of a 5,000 Ci radiological release and Lagrangian Particle Dispersion Models (LODI at LLNL/NARAC and PSPRAY at CEA) for analysis of a much larger (500,000 Ci) regional radiological release. Two densely-populated urban locations were chosen: Chicago with its high-rise skyline and gridded street network and Paris with its more consistent, lower building height and complex unaligned street network. Each location was considered under early summer daytime and nighttime conditions. Different levels of fidelity were chosen for each scale: (1) lower fidelity mass-consistent diagnostic, intermediate fidelity Navier-Stokes RANS models, and higher fidelity Navier-Stokes LES for urban-scale analysis, and (2) lower-fidelity single

  3. Innovative landfill bioreactor systems for municipal solid waste treatment in East Africa aimed at optimal energy recovery and minimal greenhouse gas emissions

    NARCIS (Netherlands)

    Salukele, F.M.

    2013-01-01

    Landfilling is currently the dominant disposal method for municipal solid waste (MSW) in developing countries. Approximately 50% of the MSW generated in East Africa is disposed in landfills. Low costs and availability of land have made landfilling the most common waste management option in East

  4. Application of AHP for the development of waste management systems that minimize infection risks in developing countries: Case studies Lesotho and South Africa

    CSIR Research Space (South Africa)

    Brent, AC

    2006-09-01

    Full Text Available -analysis approach, has been incorporated with international Life Cycle Management best practice to subsequently develop a decision support tool (WasteOpt) to optimise developing country rural Health Care Waste Management (HCWM) systems to address a main objective...

  5. Development of Compton gamma-ray sources at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Albert, F.; Anderson, S. G.; Ebbers, C. A.; Gibson, D. J.; Hartemann, F. V.; Marsh, R. A.; Messerly, M. J.; Prantil, M. A.; Wu, S.; Barty, C. P. J. [Lawrence Livermore National Laboratory, NIF and Photon Science, 7000 East avenue, Livermore, CA 94550 (United States)

    2012-12-21

    Compact Compton scattering gamma-ray sources offer the potential of studying nuclear photonics with new tools. The optimization of such sources depends on the final application, but generally requires maximizing the spectral density (photons/eV) of the gamma-ray beam while simultaneously reducing the overall bandwidth on target to minimize noise. We have developed an advanced design for one such system, comprising the RF drive, photoinjector, accelerator, and electron-generating and electron-scattering laser systems. This system uses a 120 Hz, 250 pC, 2 ps, 0.35 mm mrad electron beam with 250 MeV maximum energy in an X-band accelerator scattering off a 150 mJ, 10 ps, 532 nm laser to generate 5 Multiplication-Sign 10{sup 10} photons/eV/s/Sr at 0.5 MeV with an overall bandwidth of less than 1%. The source will be able to produce photons up to energies of 2.5 MeV. We also discuss Compton scattering gamma-ray source predictions given by numerical codes.

  6. Selection of barrier metals for a waste package in tuff

    International Nuclear Information System (INIS)

    Russell, E.W.; McCright, R.D.; O'Neal, W.C.

    1983-09-01

    The Nevada Nuclear Waste Storage Investigation (NNWSI) project under the Civilian Radioactive Waste Management Program is planning a repository at Yucca Mountain at the Nevada Test Site for isolation of high-level nuclear waste. LLNL is developing designs for an engineered barrier system containing several barriers such as the waste form, a canister and/or an overpack, packing, and near field host rock. The selection of metal containment barriers is addressed. 13 references

  7. DWTF [decontamination and waste treatment facilities] assessment

    International Nuclear Information System (INIS)

    Maimoni, A.

    1986-01-01

    The purpose of this study has been to evaluate the adequacy of present and proposed decontamination and waste treatment facilities (DWTF) at LLNL, to determine the cost effectiveness for proposed improvements, and possible alternatives for accomplishing these improvements. To the extent possible, we have also looked at some of the proposed environmental compliance and cleanup (ECC) projects

  8. Joint research and development and exchange of technology on toxic material emergency response between LLNL and ENEA. 1985 progress report

    International Nuclear Information System (INIS)

    Dickerson, M.H.; Caracciolo, R.

    1986-01-01

    For the past six years, the US Department of Energy, LLNL, and the ENEA, Rome, Italy, have participated in cooperative studies for improving a systems approach to an emergency response following nuclear accidents. Technology exchange between LLNL and the ENEA was initially confined to the development, application, and evaluation of atmospheric transport and diffusion models. With the emergence of compatible hardware configurations between LLNL and ENEA, exchanges of technology and ideas for improving the development and implementation of systems are beginning to emerge. This report describes cooperative work that has occurred during the past three years, the present state of each system, and recommendations for future exchanges of technology

  9. Experiment designs offered for discussion preliminary to an LLNL field scale validation experiment in the Yucca Mountain Exploratory Shaft Facility

    International Nuclear Information System (INIS)

    Lowry, B.; Keller, C.

    1988-01-01

    It has been proposed (''Progress Report on Experiment Rationale for Validation of LLNL Models of Ground Water Behavior Near Nuclear Waste Canisters,'' Keller and Lowry, Dec. 7, 1988) that a heat generating spent fuel canister emplaced in unsaturated tuff, in a ventilated hole, will cause a net flux of water into the borehole during the heating cycle of the spent fuel. Accompanying this mass flux will be the formation of mineral deposits near the borehole wall as the water evaporates and leaves behind its dissolved solids. The net effect of this process upon the containment of radioactive wastes is a function of (1) where and how much solid material is deposited in the tuff matrix and cracks, and (2) the resultant effect on the medium flow characteristics. Experimental concepts described in this report are designed to quantify the magnitude and relative location of solid mineral deposit formation due to a heated and vented borehole environment. The most simple tests address matrix effects only; after the process is understood in the homogeneous matrix, fracture effects would be investigated. Three experiment concepts have been proposed. Each has unique advantages and allows investigation of specific aspects of the precipitate formation process. All could be done in reasonable time (less than a year) and none of them are extremely expensive (the most expensive is probably the structurally loaded block test). The calculational ability exists to analyze the ''real'' situation and each of the experiment designs, and produce a credible series of tests. None of the designs requires the acquisition of material property data beyond current capabilities. The tests could be extended, if our understanding is consistent with the data produced, to analyze fracture effects. 7 figs

  10. DOE/LLNL verification symposium on technologies for monitoring nuclear tests related to weapons proliferation

    International Nuclear Information System (INIS)

    Nakanishi, K.K.

    1993-01-01

    The rapidly changing world situation has raised concerns regarding the proliferation of nuclear weapons and the ability to monitor a possible clandestine nuclear testing program. To address these issues, Lawrence Livermore National Laboratory's (LLNL) Treaty Verification Program sponsored a symposium funded by the US Department of Energy's (DOE) Office of Arms Control, Division of Systems and Technology. The DOE/LLNL Symposium on Technologies for Monitoring Nuclear Tests Related to Weapons Proliferation was held at the DOE's Nevada Operations Office in Las Vegas, May 6--7,1992. This volume is a collection of several papers presented at the symposium. Several experts in monitoring technology presented invited talks assessing the status of monitoring technology with emphasis on the deficient areas requiring more attention in the future. In addition, several speakers discussed proliferation monitoring technologies being developed by the DOE's weapons laboratories

  11. The LLNL Multiuser Tandem Laboratory computer-controlled radiation monitoring system

    International Nuclear Information System (INIS)

    Homann, S.G.

    1992-01-01

    The Physics Department of the Lawrence Livermore National Laboratory (LLNL) recently constructed a Multiuser Tandem Laboratory (MTL) to perform a variety of basic and applied measurement programs. The laboratory and its research equipment were constructed with support from a consortium of LLNL Divisions, Sandia National Laboratories Livermore, and the University of California. Primary design goals for the facility were inexpensive construction and operation, high beam quality at a large number of experimental stations, and versatility in adapting to new experimental needs. To accomplish these goals, our main design decisions were to place the accelerator in an unshielded structure, to make use of reconfigured cyclotrons as effective switching magnets, and to rely on computer control systems for both radiological protection and highly reproducible and well-characterized accelerator operation. This paper addresses the radiological control computer system

  12. A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

    International Nuclear Information System (INIS)

    Brumburgh, G.

    1994-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  13. Effects of stratospheric aerosol surface processes on the LLNL two-dimensional zonally averaged model

    International Nuclear Information System (INIS)

    Connell, P.S.; Kinnison, D.E.; Wuebbles, D.J.; Burley, J.D.; Johnston, H.S.

    1992-01-01

    We have investigated the effects of incorporating representations of heterogeneous chemical processes associated with stratospheric sulfuric acid aerosol into the LLNL two-dimensional, zonally averaged, model of the troposphere and stratosphere. Using distributions of aerosol surface area and volume density derived from SAGE 11 satellite observations, we were primarily interested in changes in partitioning within the Cl- and N- families in the lower stratosphere, compared to a model including only gas phase photochemical reactions

  14. Status of the SLAC/LBL/LLNL B-factory and the BABAR detector

    International Nuclear Information System (INIS)

    Oddone, P.

    1994-10-01

    After a brief introduction on the physics reach of the SLAC/LBL/LLNL Asymmetric B-Factory, the author describes the status of the accelerator and the detector as of the end of 1994. At this time, essentially all major decisions have been made, including the choice of particle identification for the detector. The author concludes this report with the description of the schedule for the construction of both accelerator and detector

  15. Evaluation of the neutron dose received by personnel at the LLNL

    International Nuclear Information System (INIS)

    Hankins, D.E.

    1982-01-01

    This report was prepared to document the techniques being used to evaluate the neutron exposures received by personnel at the LLNL. Two types of evaluations are discussed covering the use of the routine personnel dosimeter and of the albedo neutron dosimeter. Included in the report are field survey results which were used to determine the calibration factors being applied to the dosimeter readings. Calibration procedures are discussed and recommendations are made on calibration and evaluation procedures

  16. LLNL Contribution to LLE FY09 Annual Report: NIC and HED Results

    International Nuclear Information System (INIS)

    Heeter, R.F.; Landen, O.L.; Hsing, W.W.; Fournier, K.B.

    2009-01-01

    In FY09, LLNL led 238 target shots on the OMEGA Laser System. Approximately half of these LLNL-led shots supported the National Ignition Campaign (NIC). The remainder was dedicated to experiments for the high-energy-density stewardship experiments (HEDSE). Objectives of the LLNL led NIC campaigns at OMEGA included: (1) Laser-plasma interaction studies in physical conditions relevant for the NIF ignition targets; (2) Demonstration of Tr = 100 eV foot symmetry tuning using a reemission sphere; (3) X-ray scattering in support of conductivity measurements of solid density Be plasmas; (4) Experiments to study the physical properties (thermal conductivity) of shocked fusion fuels; (5) High-resolution measurements of velocity nonuniformities created by microscopic perturbations in NIF ablator materials; (6) Development of a novel Compton Radiography diagnostic platform for ICF experiments; and (7) Precision validation of the equation of state for quartz. The LLNL HEDSE campaigns included the following experiments: (1) Quasi-isentropic (ICE) drive used to study material properties such as strength, equation of state, phase, and phase-transition kinetics under high pressure; (2) Development of a high-energy backlighter for radiography in support of material strength experiments using Omega EP and the joint OMEGA-OMEGA-EP configuration; (3) Debris characterization from long-duration, point-apertured, point-projection x-ray backlighters for NIF radiation transport experiments; (4) Demonstration of ultrafast temperature and density measurements with x-ray Thomson scattering from short-pulse laser-heated matter; (5) The development of an experimental platform to study nonlocal thermodynamic equilibrium (NLTE) physics using direct-drive implosions; (6) Opacity studies of high-temperature plasmas under LTE conditions; and (7) Characterization of copper (Cu) foams for HEDSE experiments.

  17. Superconducting magnet development capability of the LLNL [Lawrence Livermore National Laboratory] High Field Test Facility

    International Nuclear Information System (INIS)

    Miller, J.R.; Shen, S.; Summers, L.T.

    1990-02-01

    This paper discusses the following topics: High-Field Test Facility Equipment at LLNL; FENIX Magnet Facility; High-Field Test Facility (HFTF) 2-m Solenoid; Cryogenic Mechanical Test Facility; Electro-Mechanical Conductor Test Apparatus; Electro-Mechanical Wire Test Apparatus; FENIX/HFTF Data System and Network Topology; Helium Gas Management System (HGMS); Airco Helium Liquefier/Refrigerator; CTI 2800 Helium Liquefier; and MFTF-B/ITER Magnet Test Facility

  18. LLNL Containment Program nuclear test effects and geologic data base: glossary and parameter definitions

    International Nuclear Information System (INIS)

    Howard, N.W.

    1983-01-01

    This report lists, defines, and updates Parameters in DBASE, an LLNL test effects data bank in which data are stored from experiments performed at NTS and other test sites. Parameters are listed by subject and by number. Part 2 of this report presents the same information for parameters for which some of the data may be classified; it was issued in 1979 and is not being reissued at this time as it is essentially unchanged

  19. 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

  20. Performance of HEPA filters at LLNL following the 1980 and 1989 earthquakes

    International Nuclear Information System (INIS)

    Bergman, W.; Elliott, J.; Wilson, K.

    1995-01-01

    The Lawrence Livermore National Laboratory has experienced two significant earthquakes for which data is available to assess the ability of HEPA filters to withstand seismic conditions. A 5.9 magnitude earthquake with an epicenter 10 miles from LLNL struck on January 24, l980. Estimates of the peak ground accelerations ranged from 0.2 to 0.3 g. A 7.0 magnitude earthquake with an epicenter about 50 miles from LLNL struck on October 17, 1989. Measurements of the ground accelerations at LLNL averaged 0.1 g. The results from the in-place filter tests obtained after each of the earthquakes were compiled and studied to determine if the earthquakes had caused filter leakage. Our study showed that only the 1980 earthquake resulted in a small increase in the number of HEPA filters developing leaks. In the 12 months following the 1980 and 1989 earthquakes, the in-place filter tests showed 8.0% and 4.1% of all filters respectively developed leaks. The average percentage of filters developing leaks from 1980 to 1993 was 3.3%+/-1.7%. The increase in the filter leaks is significant for the 1980 earthquake, but not for the 1989 earthquake. No contamination was detected following the earthquakes that would suggest transient releases from the filtration system

  1. Physics of laser fusion. Volume II. Diagnostics of experiments on laser fusion targets at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Ahlstrom, H.G.

    1982-01-01

    These notes present the experimental basis and status for laser fusion as developed at LLNL. There are two other volumes in this series: Vol. I, by C.E. Max, presents the theoretical laser-plasma interaction physics; Vol. III, by J.F. Holzrichter et al., presents the theory and design of high-power pulsed lasers. A fourth volume will present the theoretical implosion physics. The notes consist of six sections. The first, an introductory section, provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLNL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLNL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future.

  2. Performance of HEPA filters at LLNL following the 1980 and 1989 earthquakes

    Energy Technology Data Exchange (ETDEWEB)

    Bergman, W.; Elliott, J.; Wilson, K. [Lawrence Livermore National Laboratory, CA (United States)

    1995-02-01

    The Lawrence Livermore National Laboratory has experienced two significant earthquakes for which data is available to assess the ability of HEPA filters to withstand seismic conditions. A 5.9 magnitude earthquake with an epicenter 10 miles from LLNL struck on January 24, l980. Estimates of the peak ground accelerations ranged from 0.2 to 0.3 g. A 7.0 magnitude earthquake with an epicenter about 50 miles from LLNL struck on October 17, 1989. Measurements of the ground accelerations at LLNL averaged 0.1 g. The results from the in-place filter tests obtained after each of the earthquakes were compiled and studied to determine if the earthquakes had caused filter leakage. Our study showed that only the 1980 earthquake resulted in a small increase in the number of HEPA filters developing leaks. In the 12 months following the 1980 and 1989 earthquakes, the in-place filter tests showed 8.0% and 4.1% of all filters respectively developed leaks. The average percentage of filters developing leaks from 1980 to 1993 was 3.3%+/-1.7%. The increase in the filter leaks is significant for the 1980 earthquake, but not for the 1989 earthquake. No contamination was detected following the earthquakes that would suggest transient releases from the filtration system.

  3. Physics of laser fusion. Volume II. Diagnostics of experiments on laser fusion targets at LLNL

    International Nuclear Information System (INIS)

    Ahlstrom, H.G.

    1982-01-01

    These notes present the experimental basis and status for laser fusion as developed at LLNL. There are two other volumes in this series: Vol. I, by C.E. Max, presents the theoretical laser-plasma interaction physics; Vol. III, by J.F. Holzrichter et al., presents the theory and design of high-power pulsed lasers. A fourth volume will present the theoretical implosion physics. The notes consist of six sections. The first, an introductory section, provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLNL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLNL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future

  4. Taxonomic minimalism.

    Science.gov (United States)

    Beattle, A J; Oliver, I

    1994-12-01

    Biological surveys are in increasing demand while taxonomic resources continue to decline. How much formal taxonomy is required to get the job done? The answer depends on the kind of job but it is possible that taxonomic minimalism, especially (1) the use of higher taxonomic ranks, (2) the use of morphospecies rather than species (as identified by Latin binomials), and (3) the involvement of taxonomic specialists only for training and verification, may offer advantages for biodiversity assessment, environmental monitoring and ecological research. As such, formal taxonomy remains central to the process of biological inventory and survey but resources may be allocated more efficiently. For example, if formal Identification is not required, resources may be concentrated on replication and increasing sample sizes. Taxonomic minimalism may also facilitate the inclusion in these activities of important but neglected groups, especially among the invertebrates, and perhaps even microorganisms. Copyright © 1994. Published by Elsevier Ltd.

  5. Preliminary assessment of geologic materials to minimize biological intrusion of low-level waste trench covers and plans for the future

    International Nuclear Information System (INIS)

    Hakonson, T.E.; White, G.C.; Gladney, E.S.; Muller, M.

    1981-01-01

    The long-term integrity of low-level waste shallow land burial sites is dependent on the interaction of physical, chemical, and biological factors that modify the waste containment system. Past research on low-level waste shallow land burial methods has emphasized physical (i.e., water infiltration, soil erosion) and chemical (radionuclide leaching) processes that can cause radionuclide transport from a waste site. Preliminary results demonstrate that a sandy backfill material offers little resistance to root and animal intrusion through the cover profile. However, bentonite clay, cobble, and cobble-gravel combinations do reduce plant root and animal intrusion through cover profiles compared with sandy backfill soil. However, bentonite clay barrier systems appear to be degraded by plant roots through time. Desiccation of the clay barrier by invading plant roots may limit the usefulness of bentonite clay as a moisture and/or biological carrier unless due consideration is given to this interaction. Future experiments are described that further examine the effect of plant roots on clay barrier systems and that determine the effectiveness of proposed biological barriers on larger scales and under various stress conditions

  6. Institute of Geophysics and Planetary Physics (IGPP), Lawrence Livermore National Laboratory (LLNL): Quinquennial report, November 14-15, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Tweed, J.

    1996-10-01

    This Quinquennial Review Report of the Lawrence Livermore National Laboratory (LLNL) branch of the Institute for Geophysics and Planetary Physics (IGPP) provides an overview of IGPP-LLNL, its mission, and research highlights of current scientific activities. This report also presents an overview of the University Collaborative Research Program (UCRP), a summary of the UCRP Fiscal Year 1997 proposal process and the project selection list, a funding summary for 1993-1996, seminars presented, and scientific publications. 2 figs., 3 tabs.

  7. Cost-benefit analysis for waste segregation at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    1992-02-01

    This report presents a cost-benefit analysis for the segregation of mixed, hazardous, and nonhazardous wastes at Lawrence Livermore National Laboratory (LLNL). The cost-benefit analysis was conducted to determine if current waste segregation practices and additional candidates for waste segregation at LLNL might have the potential for significant waste source reduction and annual savings in treatment and disposal costs. In the following cost-benefit analysis, capital costs and recurring costs of waste segregation practices are compared to the economic benefits of savings in treatment and disposal costs. Indirect or overhead costs associated with these wastes are not available and have not been included. Not considered are additional benefits of waste segregation such as decreased potential for liability to LLNL for adverse environmental effects, improved worker safety, and enhanced LLNL image within the community because of environmental improvement. The economic evaluations in this report are presented on a Lab-wide basis. All hazardous wastes generated by a program are turned over to the Hazardous Waste Management (HWM) group, which is responsible for the storage, treatment, or disposal of these wastes and funded funded directly for this work

  8. Solid waste management

    OpenAIRE

    Srebrenkoska, Vineta; Golomeova, Saska; Zhezhova, Silvana

    2013-01-01

    Waste is unwanted or useless materials from households, industry, agriculture, hospitals. Waste materials in solid state are classified as solid waste. Increasing of the amount of solid waste and the pressure what it has on the environment, impose the need to introduce sustainable solid waste management. Advanced sustainable solid waste management involves several activities at a higher level of final disposal of the waste management hierarchy. Minimal use of material and energy resources ...

  9. Harmful Waste Process

    International Nuclear Information System (INIS)

    Ki, Mun Bong; Lee, Shi Jin; Park, Jun Seok; Yoon, Seok Pyo; Lee, Jae Hyo; Jo, Byeong Ryeol

    2008-08-01

    This book gives descriptions of processing harmful waste, including concerned law and definition of harmful waste, current conditions and generation of harmful waste in Korea, international condition of harmful waste, minimizing of generation of harmful waste, treatment and storage. It also tells of basic science for harmful waste disposal with physics, chemistry, combustion engineering, microbiology and technique of disposal such as physical, chemical, biological process, stabilizing and solidification, incineration and waste in landfill.

  10. A concept to combine DOE waste minimization goals with commercial utility needs for a universal container system for spent nuclear fuel storage, transportation, and disposal

    International Nuclear Information System (INIS)

    Falci, F.P.; Smith, M.L.; Sorenson, K.B.

    1993-01-01

    The concept of storing, transporting, and disposing of spent fuel using a single package has obvious advantages. Coupling this concept with using contaminated scrap metal from the EM Complex will help reduce a significant portion of waste that would otherwise need to be packaged, stored, and disposed of as low level radioactive waste. Assuming a material of cost of $1 per pound for 800,000 tons of metal needed for universal containers, the potential material cost savings from manufacturing these containers from what would otherwise be a waste product is about $1.5 billion. Clearly, this concept is novel and has significant obstacles that need to be addressed and overcome; particularly in the regulatory arena. However, the potential benefits warrant the evaluation of the proposal on several fronts. DOE OCRWM should seriously consider the universal cask concept for management of spent fuel. DOE EM should pursue the development of melting contaminated scrap for the manufacture of casks. Finally, EM and OCRWM should cooperate on the evaluation of using EM contaminated scrap metal for the manufacture of universal casks for OCRWM spent fuel

  11. Up-cycling waste glass to minimal water adsorption/absorption lightweight aggregate by rapid low temperature sintering: optimization by dual process-mixture response surface methodology.

    Science.gov (United States)

    Velis, Costas A; Franco-Salinas, Claudia; O'Sullivan, Catherine; Najorka, Jens; Boccaccini, Aldo R; Cheeseman, Christopher R

    2014-07-01

    Mixed color waste glass extracted from municipal solid waste is either not recycled, in which case it is an environmental and financial liability, or it is used in relatively low value applications such as normal weight aggregate. Here, we report on converting it into a novel glass-ceramic lightweight aggregate (LWA), potentially suitable for high added value applications in structural concrete (upcycling). The artificial LWA particles were formed by rapidly sintering (shrinkage during sintering, density and water adsorption/absorption. The diametrical expansion could be effectively modeled via the RSM and controlled to meet a wide range of specifications; here we optimized for LWA structural concrete. The optimally designed LWA is sintered in comparatively low temperatures (825-835 °C), thus potentially saving costs and lowering emissions; it had exceptionally low water adsorption/absorption (6.1-7.2% w/wd; optimization target: 1.5-7.5% w/wd); while remaining substantially lightweight (density: 1.24-1.28 g.cm(-3); target: 0.9-1.3 g.cm(-3)). This is a considerable advancement for designing effective environmentally friendly lightweight concrete constructions, and boosting resource efficiency of waste glass flows.

  12. The experimental investigation on the performance of a low temperature waste heat-driven multi-bed desiccant dehumidifier (MBDD) and minimization of entropy generation

    KAUST Repository

    Myat, Aung; Thu, Kyaw; Ng, K. C.

    2012-01-01

    We present the experimental investigation on the performance of multi-bed desiccant dehumidification system (MBDD) using a thermodynamic framework with an entropy generation analysis. The cyclic steady state performance of adsorption-desorption processes at the assorted heat source temperatures, and typical ambient humidity conditions was carried out. MBDD unit uses type-RD silica gel pore surface area with of 720 m 2/g. It has a nominal diameter range of 0.4 to 0. 7 mm. The key advantages of MBDD are: (i) it has no moving parts rendering less maintenance, (ii) energy-efficient means of dehumidification by adsorption process with low temperature heat source as compared to the conventional methods, (iii) although it is a pecked bed desiccant, a laminar chamber is employed by arranging the V-shaped configuration of heat exchangers and (iv) it is environmental friendly with the low-carbon footprint. Entropy generation analysis was performed at the assorted heat source temperatures to investigate the performance of MBDD. By conducting the entropy minimization, it is now able to locate the optimal operating conditions of the system while the specific entropy generation is found to be minimal. This analysis shows that the minimization of entropy generation in the dehumidification cycle leads to the maximization of COP in the MBDD and thus, higher delivery of useful effects at the same input resources. © 2011 Elsevier Ltd. All rights reserved.

  13. The experimental investigation on the performance of a low temperature waste heat-driven multi-bed desiccant dehumidifier (MBDD) and minimization of entropy generation

    KAUST Repository

    Myat, Aung

    2012-06-01

    We present the experimental investigation on the performance of multi-bed desiccant dehumidification system (MBDD) using a thermodynamic framework with an entropy generation analysis. The cyclic steady state performance of adsorption-desorption processes at the assorted heat source temperatures, and typical ambient humidity conditions was carried out. MBDD unit uses type-RD silica gel pore surface area with of 720 m 2/g. It has a nominal diameter range of 0.4 to 0. 7 mm. The key advantages of MBDD are: (i) it has no moving parts rendering less maintenance, (ii) energy-efficient means of dehumidification by adsorption process with low temperature heat source as compared to the conventional methods, (iii) although it is a pecked bed desiccant, a laminar chamber is employed by arranging the V-shaped configuration of heat exchangers and (iv) it is environmental friendly with the low-carbon footprint. Entropy generation analysis was performed at the assorted heat source temperatures to investigate the performance of MBDD. By conducting the entropy minimization, it is now able to locate the optimal operating conditions of the system while the specific entropy generation is found to be minimal. This analysis shows that the minimization of entropy generation in the dehumidification cycle leads to the maximization of COP in the MBDD and thus, higher delivery of useful effects at the same input resources. © 2011 Elsevier Ltd. All rights reserved.

  14. Contingency plan for the Lawrence Livermore National Laboratory's hazardous-waste operations

    International Nuclear Information System (INIS)

    Roberts, R.S.

    1981-01-01

    The Lawrence Livermore National Laboratory (LLNL) has the necessary equipment and trained personnel to respond to a large number of hazardous material spills and fires or other emergencies resulting from these spills including injured personnel. This response capability is further expanded by the agreements that LLNL has with a number of outside response agencies. The Hazards Control Department at LLNL functions as the central point for coordinating the response of the equipment and personnel. Emergencies involving hazardous waste are also coordinated through the Hazards Control Department, but the equipment and personnel in the Toxic Waste Control Group would be activated for large volume waste pumpouts. Descriptions of response equipment, hazardous waste locations communication systems, and procedures for personnel involved in the emergency are provided

  15. A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

    International Nuclear Information System (INIS)

    Brumburgh, G.P.

    1995-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  16. Status of the SLAC/LBL/LLNL B-Factory and the BaBar detector

    International Nuclear Information System (INIS)

    Oddone, P.

    1994-08-01

    The primary motivation of the Asymmetric B-Factory is the study of CP violation. The decay of B mesons and, in particular, the decay of neutral B mesons, offers the possibility of determining conclusively whether CP violation is part and parcel of the Standard Model with three generations of quarks and leptons. Alternatively, the authors may discover that CP violation lies outside the present framework. In this paper the authors briefly describe the physics reach of the SLAC/LBL/LLNL Asymmetric B-Factory, the progress on the machine design and construction, the progress on the detector design, and the schedule to complete both projects

  17. M4FT-15LL0806062-LLNL Thermodynamic and Sorption Data FY15 Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Zavarin, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wolery, T. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-08-31

    This progress report (Milestone Number M4FT-15LL0806062) summarizes research conducted at Lawrence Livermore National Laboratory (LLNL) within Work Package Number FT-15LL080606. The focus of this research is the thermodynamic modeling of Engineered Barrier System (EBS) materials and properties and development of thermodynamic databases and models to evaluate the stability of EBS materials and their interactions with fluids at various physicochemical conditions relevant to subsurface repository environments. The development and implementation of equilibrium thermodynamic models are intended to describe chemical and physical processes such as solubility, sorption, and diffusion.

  18. Analyses in Support of Z-IFE LLNL Progress Report for FY-05

    International Nuclear Information System (INIS)

    Moir, R W; Abbott, R P; Callahan, D A; Latkowski, J F; Meier, W R; Reyes, S

    2005-01-01

    The FY04 LLNL study of Z-IFE [1] proposed and evaluated a design that deviated from SNL's previous baseline design. The FY04 study included analyses of shock mitigation, stress in the first wall, neutronics and systems studies. In FY05, the subject of this report, we build on our work and the theme of last year. Our emphasis continues to be on alternatives that hold promise of considerable improvements in design and economics compared to the base-line design. Our key results are summarized here

  19. The Auburn Engineering Technical Assistance Program investigation of polyvinyl alcohol film developments pertaining to radioactive particle decontamination and industrial waste minimization

    Science.gov (United States)

    Mole, Tracey Lawrence

    In this work, an effective and systematic model is devised to synthesize the optimal formulation for an explicit engineering application in the nuclear industry, i.e. radioactive decontamination and waste reduction. Identification of an optimal formulation that is suitable for the desired system requires integration of all the interlacing behaviors of the product constituents. This work is unique not only in product design, but also in these design techniques. The common practice of new product development is to design the optimized product for a particular industrial niche and then subsequent research for the production process is conducted, developed and optimized separately from the product formulation. In this proposed optimization design technique, the development process, disposal technique and product formulation is optimized simultaneously to improve production profit, product behavior and disposal emissions. This "cradle to grave" optimization approach allowed a complex product formulation development process to be drastically simplified. The utilization of these modeling techniques took an industrial idea to full scale testing and production in under 18 months by reducing the number of subsequent laboratory trials required to optimize the formula, production and waste treatment aspects of the product simultaneously. This particular development material involves the use of a polymer matrix that is applied to surfaces as part of a decontamination system. The polymer coating serves to initially "fix" the contaminants in place for detection and ultimate elimination. Upon mechanical entrapment and removal, the polymer coating containing the radioactive isotopes can be dissolved in a solvent processor, where separation of the radioactive metallic particles can take place. Ultimately, only the collection of divided solids should be disposed of as nuclear waste. This creates an attractive alternative to direct land filling or incineration. This philosophy also

  20. Federal facilities compliance act waste management

    International Nuclear Information System (INIS)

    Bowers, J.; Gates-Anderson, D.; Hollister, R.; Painter, S.

    1999-01-01

    Site Treatment Plans (STPs) developed through the Federal Facilities Compliance Act pose many technical and administrative challenges. Legacy wastes managed under these plans require Land Disposal Restriction (LDR) compliance through treatment and ultimate disposal. Although capacity has been defined for most of the Department of Energy wastes, many waste streams require further characterization and many need additional treatment and handling beyond LDR criteria to be able to dispose of the waste. At Lawrence Livermore National Laboratory (LLNL), the Hazardous Waste Management Division has developed a comprehensive Legacy Waste Program. The program directs work to manage low level and mixed wastes to ensure compliance with nuclear facility rules and its STP. This paper provides a survey of work conducted on these wastes at LLNL. They include commercial waste treatment and disposal, diverse forms of characterization, inventory maintenance and reporting, on-site treatment, and treatability studies. These activities are conducted in an integrated fashion to meet schedules defined in the STP. The processes managing wastes are dynamic due to required integration of administrative, regulatory, and technical concerns spanning the gamut to insure safe proper disposal

  1. Replacement of chemical oxygen demand (COD) with total organic carbon (TOC) for monitoring wastewater treatment performance to minimize disposal of toxic analytical waste.

    Science.gov (United States)

    Dubber, Donata; Gray, Nicholas F

    2010-10-01

    Chemical oxygen demand (COD) is widely used for wastewater monitoring, design, modeling and plant operational analysis. However this method results in the production of hazardous wastes including mercury and hexavalent chromium. The study examined the replacement of COD with total organic carbon (TOC) for general performance monitoring by comparing their relationship with influent and effluent samples from 11 wastewater treatment plants. Biochemical oxygen demand (BOD5) was also included in the comparison as a control. The results show significant linear relationships between TOC, COD and BOD5 in settled (influent) domestic and municipal wastewaters, but only between COD and TOC in treated effluents. The study concludes that TOC can be reliably used for the generic replacement of both COD (COD=49.2+3.00*TOC) and BOD5 (BOD5=23.7+1.68*TOC) in influent wastewaters but only for COD (COD=7.25+2.99*TOC) in final effluents.

  2. Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)

    International Nuclear Information System (INIS)

    Riley, D.; Dodson, K.

    2007-01-01

    This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched

  3. Over Batch Analysis for the LLNL DOE-STD-3013 Packaging System

    International Nuclear Information System (INIS)

    Riley, D.C.; Dodson, K.

    2009-01-01

    This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched.

  4. LLNL Experimental Test Site (Site 300) Potable Water System Operations Plan

    Energy Technology Data Exchange (ETDEWEB)

    Ocampo, R. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-14

    The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

  5. Waste Isolation Pilot Plant Technical Assessment Team Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-17

    This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

  6. Pollution Prevention, Waste Minimization and Material Recycling Successes Realized during Savannah River Site's K Area Materials Storage (KAMS) Project, W226

    International Nuclear Information System (INIS)

    Ellis, M.S.

    2001-01-01

    As DOE continues to forge ahead and re-evaluate post cold war missions, facilities that were constructed and operated for DOE/DOD over the past 50+ years are coming to the end of their useful life span. These various facilities throughout the country had served a very useful purpose in our nations history; however, their time of Cold War materials production has come to an end. With this looming finalization comes a decision as to how to remedy their existence: D and R the facilities and return to ''Greenfield''; or, retrofit the existing facilities to accommodate the newer missions of the DOE Complex. The 105-K Reactor Building located at the Savannah River Site in Aiken, South Carolina was retrofit on an accelerated project schedule for a new mission called K-Area Materials Storage (KAMS). Modifications to the former defense reactor's building and equipment will allow storage of Plutonium from the Rocky Flats Site in Colorado and other materials deemed necessary by the Department of Energy. Proper project planning and activity sequencing allowed the DOE and the Westinghouse Savannah River Company to realize savings from: the recycling and/or reuse of modified facility components; reduction and reclassification of waste; reduction in radiological area footprint (rollbacks)

  7. Waste package materials selection process

    International Nuclear Information System (INIS)

    Roy, A.K.; Fish, R.L.; McCright, R.D.

    1994-01-01

    The office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating a site at Yucca Mountain in Southern Nevada to determine its suitability as a mined geologic disposal system (MGDS) for the disposal of high-level nuclear waste (HLW). The B ampersand W Fuel Company (BWFC), as a part of the Management and Operating (M ampersand O) team in support of the Yucca Mountain Site Characterization Project (YMP), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) is responsible for testing materials and developing models for the materials to be used in the waste package. This paper is aimed at presenting the selection process for materials needed in fabricating the different components of the waste package

  8. A step by step selection method for the location and the size of a waste-to-energy facility targeting the maximum output energy and minimization of gate fee.

    Science.gov (United States)

    Kyriakis, Efstathios; Psomopoulos, Constantinos; Kokkotis, Panagiotis; Bourtsalas, Athanasios; Themelis, Nikolaos

    2017-06-23

    This study attempts the development of an algorithm in order to present a step by step selection method for the location and the size of a waste-to-energy facility targeting the maximum output energy, also considering the basic obstacle which is in many cases, the gate fee. Various parameters identified and evaluated in order to formulate the proposed decision making method in the form of an algorithm. The principle simulation input is the amount of municipal solid wastes (MSW) available for incineration and along with its net calorific value are the most important factors for the feasibility of the plant. Moreover, the research is focused both on the parameters that could increase the energy production and those that affect the R1 energy efficiency factor. Estimation of the final gate fee is achieved through the economic analysis of the entire project by investigating both expenses and revenues which are expected according to the selected site and outputs of the facility. In this point, a number of commonly revenue methods were included in the algorithm. The developed algorithm has been validated using three case studies in Greece-Athens, Thessaloniki, and Central Greece, where the cities of Larisa and Volos have been selected for the application of the proposed decision making tool. These case studies were selected based on a previous publication made by two of the authors, in which these areas where examined. Results reveal that the development of a «solid» methodological approach in selecting the site and the size of waste-to-energy (WtE) facility can be feasible. However, the maximization of the energy efficiency factor R1 requires high utilization factors while the minimization of the final gate fee requires high R1 and high metals recovery from the bottom ash as well as economic exploitation of recovered raw materials if any.

  9. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  10. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  11. Reuse of waste cutting sand at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Mathews, S.; Wilson, K.

    1998-01-01

    Lawrence Livermore National Laboratory (LLNL) examined the waste stream from a water jet cutting operation, to evaluate the possible reuse of waste garnet sand. The sand is a cutting agent used to shape a variety of materials, including metals. Nearly 70,000 pounds of waste sand is generated annually by the cutting operation. The Environmental Protection Department evaluated two potential reuses for the spent garnet sand: backfill in utility trenches; and as a concrete constituent. In both applications, garnet waste would replace the sand formerly purchased by LLNL for these purposes. Findings supported the reuse of waste garnet sand in concrete, but disqualified its proposed application as trench backfill. Waste sand stabilized in a concrete matrix appeared to present no metals-leaching hazard; however, unconsolidated sand in trenches could potentially leach metals in concentrations high enough to threaten ground water quality. A technical report submitted to the San Francisco Bay Regional Water Quality Control Board was reviewed and accepted by that body. Reuse of waste garnet cutting sand as a constituent in concrete poured to form walkways and patios at LLNL was approved

  12. Overview of the LBL/LLNL negative-ion-based neutral beam program

    International Nuclear Information System (INIS)

    Pyle, R.V.

    1980-01-01

    The LBL/LLNL negative-ion-based neutral beam development program and status are described. The emphasis has shifted in some details since the first symposium in 1977, but our overall objectives remain the same, namely, the development of megawatt d.c. injection systems. Previous emphasis was on a system in which the negative ions were produced by double charge exchange in sodium vapor. At present, the emphasis is on a self-extraction source in which the negative ions are produced on a biased surface imbedded in a plasma. A one-ampere beam will be accelerated to at least 40 keV next year. Studies of negative-ion formation and interactions help provide a data base for the technology program

  13. Research at Clark in the early '60s and at LLNL in the late '80s

    International Nuclear Information System (INIS)

    Gatrousis, C.

    1993-01-01

    Tom Sugihara's scientific leadership over a period of almost four decades covered many areas. His early research at Clark dealt with fission yields measurements and radiochemical separations of fallout species in the marine environment. Tom pioneered many of the methods for detecting soft beta emitters and low levels of radioactivity. Studies of the behavior of radioactivity in the marine ecosystem were important adjuncts to Tom's nuclear science research at Clark University which emphasized investigations of nuclear reaction mechanisms. Among Tom's most important contributions while at Clark was his work with Matsuo and Dudey on the interpretation of isomeric yield ratios and fission studies with Noshkin and Baba. Tom's scientific career oscillated between research and administration. During the latter part of his career his great breadth of interests and his scientific open-quotes tasteclose quotes had a profound influence at LLNL in areas that were new to him, materials science and solid state physics

  14. A historical perspective on fifteen years of laser damage thresholds at LLNL

    International Nuclear Information System (INIS)

    Rainer, F.; De Marco, F.P.; Staggs, M.C.; Kozlowski, M.R.; Atherton, L.J.; Sheehan, L.M.

    1993-01-01

    We have completed a fifteen year, referenced and documented compilation of more than 15,000 measurements of laser-induced damage thresholds (LIDT) conducted at the Lawrence Livermore National Laboratory (LLNL). These measurements cover the spectrum from 248 to 1064 nm with pulse durations ranging from < 1 ns to 65 ns and at pulse-repetition frequencies (PRF) from single shots to 6.3 kHz. We emphasize the changes in LIDTs during the past two years since we last summarized our database. We relate these results to earlier data concentrating on improvements in processing methods, materials, and conditioning techniques. In particular, we highlight the current status of anti-reflective (AR) coatings, high reflectors (HR), polarizers, and frequency-conversion crystals used primarily at 355 nm and 1064 nm

  15. Production of High Harmonic X-Ray Radiation from Non-linear Thomson at LLNL PLEIADES

    CERN Document Server

    Lim, Jae; Betts, Shawn; Crane, John; Doyuran, Adnan; Frigola, Pedro; Gibson, David J; Hartemann, Fred V; Rosenzweig, James E; Travish, Gil; Tremaine, Aaron M

    2005-01-01

    We describe an experiment for production of high harmonic x-ray radiation from Thomson backscattering of an ultra-short high power density laser by a relativistic electron beam at the PLEIADES facility at LLNL. In this scenario, electrons execute a “figure-8” motion under the influence of the high-intensity laser field, where the constant characterizing the field strength is expected to exceed unity: $aL=e*EL/m*c*ωL ≥ 1$. With large $aL$ this motion produces high harmonic x-ray radiation and significant broadening of the spectral peaks. This paper is intended to give a layout of the PLEIADES experiment, along with progress towards experimental goals.

  16. Advanced robotics technology applied to mixed waste characterization, sorting and treatment

    International Nuclear Information System (INIS)

    Wilhelmsen, K.; Hurd, R.; Grasz, E.

    1994-04-01

    There are over one million cubic meters of radioactively contaminated hazardous waste, known as mixed waste, stored at Department of Energy facilities. Researchers at Lawrence Livermore National Laboratory (LLNL) are developing methods to safely and efficiently treat this type of waste. LLNL has automated and demonstrated a means of segregating items in a mixed waste stream. This capability incorporates robotics and automation with advanced multi-sensor information for autonomous and teleoperational handling of mixed waste items with previously unknown characteristics. The first phase of remote waste stream handling was item singulation; the ability to remove individual items of heterogeneous waste directly from a drum, box, bin, or pile. Once objects were singulated, additional multi-sensory information was used for object classification and segregation. In addition, autonomous and teleoperational surface cleaning and decontamination of homogeneous metals has been demonstrated in processing mixed waste streams. The LLNL waste stream demonstration includes advanced technology such as object classification algorithms, identification of various metal types using active and passive gamma scans and RF signatures, and improved teleoperational and autonomous grasping of waste objects. The workcell control program used an off-line programming system as a server to perform both simulation control as well as actual hardware control of the workcell. This paper will discuss the motivation for remote mixed waste stream handling, the overall workcell layout, sensor specifications, workcell supervisory control, 3D vision based automated grasp planning and object classification algorithms

  17. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Laycak, D.T.

    2010-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  18. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2008-06-16

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

  19. Final report for the 1996 DOE grant supporting research at the SLAC/LBNL/LLNL B factory

    International Nuclear Information System (INIS)

    Judd, D.; Wright, D.

    1997-01-01

    This final report discusses Department of Energy-supported research funded through Lawrence Livermore National Laboratory (LLNL) which was performed as part of a collaboration between LLNL and Prairie View A and M University to develop part of the BaBar detector at the SLAC B Factory. This work focuses on the Instrumented Flux Return (IFR) subsystem of BaBar and involves a full range of detector development activities: computer simulations of detector performance, creation of reconstruction algorithms, and detector hardware R and D. Lawrence Livermore National Laboratory has a leading role in the IFR subsystem and has established on-site computing and detector facilities to conduct this research. By establishing ties with the existing LLNL Research Collaboration Program and leveraging LLNL resources, the experienced Prairie View group was able to quickly achieve a more prominent role within the BaBar collaboration and make significant contributions to the detector design. In addition, this work provided the first entry point for Historically Black Colleges and Universities into the B Factory collaboration, and created an opportunity to train a new generation of minority students at the premier electron-positron high energy physics facility in the US

  20. Radwaste minimization successes at Duke Power Company

    International Nuclear Information System (INIS)

    Lan, C.D.; Johnson, G.T.; Groves, D.C.; Smith, T.A.

    1996-01-01

    At Duke Power Company, open-quotes Culture Changeclose quotes is a common term that we have used to describe the incredible transformation. We are becoming a cost conscious, customer driven, highly competitive business. Nowhere has this change been more evident then in the way we process and dispose of our solid radioactive waste. With top-down management support, we have used team-based, formalized problem solving methods and have implemented many successful waste minimization programs. Through these programs, we have dramatically increased employees' awareness of the importance of waste minimization. As a result, we have been able to reduce both our burial volumes and our waste processing and disposal costs. In June, 1994, we invited EPRI to conduct assessments of our waste minimization programs at Oconee and Catawba nuclear stations. Included in the assessments were in-depth looks at contamination control, an inventory of items in the plant, the volume of waste generated in the plant and how it was processed, laundry reject data, site waste-handling operations, and plant open-quotes housekeepingclose quotes routines and process. One of the most important aspects of the assessment is the open-quotes dumpster dive,close quotes which is an evaluation of site dry active waste composition by sorting through approximately fifteen bags of radioactive waste. Finally, there was an evaluation of consumable used at each site in order to gain knowledge of items that could be standardized at all stations. With EPRI recommendations, we made several changes and standardized the items used. We have made significant progress in waste reduction. We realize, however, that we are aiming at a moving target and we still have room for improvement. As the price of processing and disposal (or storage) increases, we will continue to evaluate our waste minimization programs

  1. Co-treatment of flotation waste, neutralization sludge, and arsenic-containing gypsum sludge from copper smelting: solidification/stabilization of arsenic and heavy metals with minimal cement clinker.

    Science.gov (United States)

    Liu, De-Gang; Min, Xiao-Bo; Ke, Yong; Chai, Li-Yuan; Liang, Yan-Jie; Li, Yuan-Cheng; Yao, Li-Wei; Wang, Zhong-Bing

    2018-03-01

    Flotation waste of copper slag (FWCS), neutralization sludge (NS), and arsenic-containing gypsum sludge (GS), both of which are difficult to dispose of, are major solid wastes produced by the copper smelting. This study focused on the co-treatment of FWCS, NS, and GS for solidification/stabilization of arsenic and heavy metals with minimal cement clinker. Firstly, the preparation parameters of binder composed of FWCS, NS, and cement clinker were optimized to be FWCS dosage of 40%, NS dosage of 10%, cement clinker dosage of 50%, mill time of 1.5 h, and water-to-binder ratio of 0.25. On these conditions, the unconfined compressive strength (UCS) of the binder reached 43.24 MPa after hydration of 28 days. Then, the binder was used to solidify/stabilize the As-containing GS. When the mass ratio of binder-to-GS was 5:5, the UCS of matrix can reach 11.06 MPa after hydration of 28 days, meeting the required UCS level of MU10 brick in China. Moreover, arsenic and other heavy metals in FWCS, NS, and GS were effectively solidified or stabilized. The heavy metal concentrations in leachate were much lower than those in the limits of China standard leaching test (CSLT). Therefore, the matrices were potential to be used as bricks in some constructions. XRD analysis shows that the main hydration products of the matrix were portlandite and calcium silicate hydrate. These hydration products may play a significant role in the stabilization/solidification of arsenic and heavy metals.

  2. Municipal Solid Waste Resources

    Energy Technology Data Exchange (ETDEWEB)

    None

    2016-06-01

    Municipal solid waste (MSW) is a source of biomass material that can be utilized for bioenergy production with minimal additional inputs. MSW resources include mixed commercial and residential garbage such as yard trimmings, paper and paperboard, plastics, rubber, leather, textiles, and food wastes. Waste resources such as landfill gas, mill residues, and waste grease are already being utilized for cost-effective renewable energy generation. MSW for bioenergy also represents an opportunity to divert greater volumes of residential and commercial waste from landfills.

  3. The minimally tuned minimal supersymmetric standard model

    International Nuclear Information System (INIS)

    Essig, Rouven; Fortin, Jean-Francois

    2008-01-01

    The regions in the Minimal Supersymmetric Standard Model with the minimal amount of fine-tuning of electroweak symmetry breaking are presented for general messenger scale. No a priori relations among the soft supersymmetry breaking parameters are assumed and fine-tuning is minimized with respect to all the important parameters which affect electroweak symmetry breaking. The superpartner spectra in the minimally tuned region of parameter space are quite distinctive with large stop mixing at the low scale and negative squark soft masses at the high scale. The minimal amount of tuning increases enormously for a Higgs mass beyond roughly 120 GeV

  4. Impact of the Revised 10 CFR 835 on the Neutron Dose Rates at LLNL

    International Nuclear Information System (INIS)

    Radev, R.

    2009-01-01

    In June 2007, 10 CFR 835 (1) was revised to include new radiation weighting factors for neutrons, updated dosimetric models, and dose terms consistent with the newer ICRP recommendations. A significant aspect of the revised 10 CFR 835 is the adoption of the recommendations outlined in ICRP-60 (2). The recommended new quantities demand a review of much of the basic data used in protection against exposure to sources of ionizing radiation. The International Commission on Radiation Units and Measurements has defined a number of quantities for use in personnel and area monitoring (3,4,5) including the ambient dose equivalent H*(d) to be used for area monitoring and instrument calibrations. These quantities are used in ICRP-60 and ICRP-74. This report deals only with the changes in the ambient dose equivalent and ambient dose rate equivalent for neutrons as a result of the implementation of the revised 10 CFR 835. In the report, the terms neutron dose and neutron dose rate will be used for convenience for ambient neutron dose and ambient neutron dose rate unless otherwise stated. This report provides a qualitative and quantitative estimate of how much the neutron dose rates at LLNL will change with the implementation of the revised 10 CFR 835. Neutron spectra and dose rates from selected locations at the LLNL were measured with a high resolution spectroscopic neutron dose rate system (ROSPEC) as well as with a standard neutron rem meter (a.k.a., a remball). The spectra obtained at these locations compare well with the spectra from the Radiation Calibration Laboratory's (RCL) bare californium source that is currently used to calibrate neutron dose rate instruments. The measurements obtained from the high resolution neutron spectrometer and dose meter ROSPEC and the NRD dose meter compare within the range of ±25%. When the new radiation weighting factors are adopted with the implementation of the revised 10 CFR 835, the measured dose rates will increase by up to 22%. The

  5. 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

  6. Hazardous Waste Minimization Assessment: Fort Ord, CA

    Science.gov (United States)

    1991-06-01

    phthalocyanine sludge with chromium/lead pigments, oils, hydrocarbon solvents, waxes, cobalt/zinc, magneze oleates, plasticizers Making gravure cylinders acid...7896 10920 Paint Shops 11525 190 506 8294 1598 937 Photography, Printing. and Arts) Cnts Shops 11031 310 160 150 200 10191 20 Other 4105 80 3515 510

  7. Hazardous Waste Minimization Assessment: Fort Meade, MD

    Science.gov (United States)

    1991-01-01

    Aooessloo For NTIS GRA61 DTIC TAB 0 Unannounced Justiricatlon Dy Distribution/ Availabilit !Y Code$ Avail ad/or M-t Spool 2 CONTENTS Page ’SF 298 1...26 History/Geography 26 Tenants 26 Environmental Programs 26 Air Pollution Control 27 Water Pollution Control 27 Radiation...Solvmt-lausd Faints. Product Substitution - Powder Coatings 86 Solvemt.lassd Paints - Product Substitution • Water -Baud Formulations 87 Solvent-Bad

  8. LLNL-G3Dv3: Global P wave tomography model for improved regional and teleseismic travel time prediction: LLNL-G3DV3---GLOBAL P WAVE TOMOGRAPHY

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, N. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Myers, S. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Johannesson, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Matzel, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2012-10-06

    [1] We develop a global-scale P wave velocity model (LLNL-G3Dv3) designed to accurately predict seismic travel times at regional and teleseismic distances simultaneously. The model provides a new image of Earth's interior, but the underlying practical purpose of the model is to provide enhanced seismic event location capabilities. The LLNL-G3Dv3 model is based on ∼2.8 millionP and Pnarrivals that are re-processed using our global multiple-event locator called Bayesloc. We construct LLNL-G3Dv3 within a spherical tessellation based framework, allowing for explicit representation of undulating and discontinuous layers including the crust and transition zone layers. Using a multiscale inversion technique, regional trends as well as fine details are captured where the data allow. LLNL-G3Dv3 exhibits large-scale structures including cratons and superplumes as well numerous complex details in the upper mantle including within the transition zone. Particularly, the model reveals new details of a vast network of subducted slabs trapped within the transition beneath much of Eurasia, including beneath the Tibetan Plateau. We demonstrate the impact of Bayesloc multiple-event location on the resulting tomographic images through comparison with images produced without the benefit of multiple-event constraints (single-event locations). We find that the multiple-event locations allow for better reconciliation of the large set of direct P phases recorded at 0–97° distance and yield a smoother and more continuous image relative to the single-event locations. Travel times predicted from a 3-D model are also found to be strongly influenced by the initial locations of the input data, even when an iterative inversion/relocation technique is employed.

  9. LLNL Underground-Coal-Gasification Project. Quarterly progress report, July-September 1981

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, D.R.; Clements, W. (eds.)

    1981-11-09

    We have continued our laboratory studies of forward gasification in small blocks of coal mounted in 55-gal drums. A steam/oxygen mixture is fed into a small hole drilled longitudinally through the center of the block, the coal is ignited near the inlet and burns toward the outlet, and the product gases come off at the outlet. Various diagnostic measurements are made during the course of the burn, and afterward the coal block is split open so that the cavity can be examined. Development work continues on our mathematical model for the small coal block experiments. Preparations for the large block experiments at a coal outcrop in the Tono Basin of Washington State have required steadily increasing effort with the approach of the scheduled starting time for the experiments (Fall 1981). Also in preparation is the deep gasification experiment, Tono 1, planned for another site in the Tono Basin after the large block experiments have been completed. Wrap-up work continues on our previous gasification experiments in Wyoming. Results of the postburn core-drilling program Hoe Creek 3 are presented here. Since 1976 the Soviets have been granted four US patents on various aspects of the underground coal gasification process. These patents are described here, and techniques of special interest are noted. Finally, we include ten abstracts of pertinent LLNL reports and papers completed during the quarter.

  10. Status of experiments at LLNL on high-power X-band microwave generators

    International Nuclear Information System (INIS)

    Houck, T.L.; Westenskow, G.A.

    1994-01-01

    The Microwave Source Facility at the Lawrence Livermore National Laboratory (LLNL) is studying the application of induction accelerator technology to high-power microwave generators suitable for linear collider power sources. The authors report on the results of two experiments, both using the Choppertron's 11.4 GHz modulator and a 5-MeV, 1-kA induction beam. The first experimental configuration has a single traveling wave output structure designed to produce in excess of 300 MW in a single fundamental waveguide. This output structure consists of 12 individual cells, the first two incorporating de-Q-ing circuits to dampen higher order resonant modes. The second experiment studies the feasibility of enhancing beam to microwave power conversion by accelerating a modulated beam with induction cells. Referred to as the ''Reacceleration Experiment,'' this experiment consists of three traveling-wave output structures designed to produce about 125 MW per output and two induction cells located between the outputs. Status of current and planned experiments are presented

  11. Pleiades: A Sub-picosecond Tunable X-ray Source at the LLNL Electron Linac

    International Nuclear Information System (INIS)

    Slaughter, Dennis; Springer, Paul; Le Sage, Greg; Crane, John; Ditmire, Todd; Cowan, Tom; Anderson, Scott G.; Rosenzweig, James B.

    2002-01-01

    The use of ultra fast laser pulses to generate very high brightness, ultra short (fs to ps) pulses of x-rays is a topic of great interest to the x-ray user community. In principle, femto-second-scale pump-probe experiments can be used to temporally resolve structural dynamics of materials on the time scale of atomic motion. The development of sub-ps x-ray pulses will make possible a wide range of materials and plasma physics studies with unprecedented time resolution. A current project at LLNL will provide such a novel x-ray source based on Thomson scattering of high power, short laser pulses with a high peak brightness, relativistic electron bunch. The system is based on a 5 mm-mrad normalized emittance photo-injector, a 100 MeV electron RF linac, and a 300 mJ, 35 fs solid-state laser system. The Thomson x-ray source produces ultra fast pulses with x-ray energies capable of probing into high-Z metals, and a high flux per pulse enabling single shot experiments. The system will also operate at a high repetition rate (∼ 10 Hz). (authors)

  12. The EBIT Calorimeter Spectrometer: a new, permanent user facility at the LLNL EBIT

    International Nuclear Information System (INIS)

    Porter, F.S.; Beiersdorfer, P.; Brown, G.V.; Doriese, W.; Gygax, J.; Kelley, R.L.; Kilbourne, C.A.; King, J.; Irwin, K.; Reintsema, C.; Ullom, J.

    2007-01-01

    The EBIT Calorimeter Spectrometer (ECS) is currently being completed and will be installed at the EBIT facility at the Lawrence Livermore National Laboratory in October 2007. The ECS will replace the smaller XRS/EBIT microcalorimeter spectrometer that has been in almost continuous operation since 2000. The XRS/EBIT was based on a spare laboratory cryostat and an engineering model detector system from the Suzaku/XRS observatory program. The new ECS spectrometer was built to be a low maintenance, high performance implanted silicon microcalorimeter spectrometer with 4 eV resolution at 6 keV, 32 detector channels, 10 (micro)s event timing, and capable of uninterrupted acquisition sessions of over 60 hours at 50 mK. The XRS/EBIT program has been very successful, producing many results on topics such as laboratory astrophysics, atomic physics, nuclear physics, and calibration of the spectrometers for the National Ignition Facility. The ECS spectrometer will continue this work into the future with improved spectral resolution, integration times, and ease-of-use. We designed the ECS instrument with TES detectors in mind by using the same highly successful magnetic shielding as our laboratory TES cryostats. This design will lead to a future TES instrument at the LLNL EBIT. Here we discuss the legacy of the XRS/EBIT program, the performance of the new ECS spectrometer, and plans for a future TES instrument.

  13. Overview and applications of the Monte Carlo radiation transport kit at LLNL

    International Nuclear Information System (INIS)

    Sale, K. E.

    1999-01-01

    Modern Monte Carlo radiation transport codes can be applied to model most applications of radiation, from optical to TeV photons, from thermal neutrons to heavy ions. Simulations can include any desired level of detail in three-dimensional geometries using the right level of detail in the reaction physics. The technology areas to which we have applied these codes include medical applications, defense, safety and security programs, nuclear safeguards and industrial and research system design and control. The main reason such applications are interesting is that by using these tools substantial savings of time and effort (i.e. money) can be realized. In addition it is possible to separate out and investigate computationally effects which can not be isolated and studied in experiments. In model calculations, just as in real life, one must take care in order to get the correct answer to the right question. Advancing computing technology allows extensions of Monte Carlo applications in two directions. First, as computers become more powerful more problems can be accurately modeled. Second, as computing power becomes cheaper Monte Carlo methods become accessible more widely. An overview of the set of Monte Carlo radiation transport tools in use a LLNL will be presented along with a few examples of applications and future directions

  14. The minimal non-minimal standard model

    International Nuclear Information System (INIS)

    Bij, J.J. van der

    2006-01-01

    In this Letter I discuss a class of extensions of the standard model that have a minimal number of possible parameters, but can in principle explain dark matter and inflation. It is pointed out that the so-called new minimal standard model contains a large number of parameters that can be put to zero, without affecting the renormalizability of the model. With the extra restrictions one might call it the minimal (new) non-minimal standard model (MNMSM). A few hidden discrete variables are present. It is argued that the inflaton should be higher-dimensional. Experimental consequences for the LHC and the ILC are discussed

  15. Report on the B-Fields at NIF Workshop Held at LLNL October 12-13, 2015

    International Nuclear Information System (INIS)

    Fournier, K. B.; Moody, J. D.

    2015-01-01

    A national ICF laboratory workshop on requirements for a magnetized target capability on NIF was held by NIF at LLNL on October 12 and 13, attended by experts from LLNL, SNL, LLE, LANL, GA, and NRL. Advocates for indirect drive (LLNL), magnetic (Z) drive (SNL), polar direct drive (LLE), and basic science needing applied B (many institutions) presented and discussed requirements for the magnetized target capabilities they would like to see. 30T capability was most frequently requested. A phased operation increasing the field in steps experimentally can be envisioned. The NIF management will take the inputs from the scientific community represented at the workshop and recommend pulse-powered magnet parameters for NIF that best meet the collective user requests. In parallel, LLNL will continue investigating magnets for future generations that might be powered by compact laser-B-field generators (Moody, Fujioka, Santos, Woolsey, Pollock). The NIF facility engineers will start to analyze compatibility of the recommended pulsed magnet parameters (size, field, rise time, materials) with NIF chamber constraints, diagnostic access, and final optics protection against debris in FY16. The objective of this assessment will be to develop a schedule for achieving an initial Bfield capability. Based on an initial assessment, room temperature magnetized gas capsules will be fielded on NIF first. Magnetized cryo-ice-layered targets will take longer (more compatibility issues). Magnetized wetted foam DT targets (Olson) may have somewhat fewer compatibility issues making them a more likely choice for the first cryo-ice-layered target fielded with applied Bz.

  16. Joint research and development on toxic-material emergency response between ENEA and LLNL. 1982 progress report

    International Nuclear Information System (INIS)

    Gudiksen, P.; Lange, R.; Dickerson, M.; Sullivan, T.; Rosen, L.; Walker, H.; Boeri, G.B.; Caracciolo, R.; Fiorenza, R.

    1982-11-01

    A summary is presented of current and future cooperative studies between ENEA and LLNL researchers designed to develop improved real-time emergency response capabilities for assessing the environmental consequences resulting from an accidental release of toxic materials into the atmosphere. These studies include development and evaluation of atmospheric transport and dispersion models, interfacing of data processing and communications systems, supporting meteorological field experiments, and integration of radiological measurements and model results into real-time assessments

  17. Fabrication and closure development of nuclear waste containers for storage at the Yucca Mountain, Nevada repository

    International Nuclear Information System (INIS)

    Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

    1989-04-01

    US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 1 fig., 7 tabs

  18. An assessment of potential risk resulting from a maximum credible accident scenario at the proposed explosive waste storage facility (EWSF)

    International Nuclear Information System (INIS)

    Otsuki, K.; Harrach, R.; Berger, R.

    1992-10-01

    Lawrence Livermore National Laboratory (LLNL) proposes to build, permit, and operate a storage facility for explosive wastes at LLNL's Explosive Test Site, Site 300. The facility would consist of four existing magazines, four new magazettes (small concrete vaults), and a new prefabricated metal building. Ash from on-site treatment of explosive waste would also be stored in the prefabricated metal building prior to sampling analysis, and shipment. The magazettes would be installed at each magazine-and would provide segregated storage for explosive waste types including detonators, actuators, and other initiating devices. The proposed facility would be used to store explosive wastes generated by the Hydrotest and Explosive Development Programs at LLNL prior to treatment on-site or shipment to permitted, commercial, off-site treatment facilities. Explosive wastes to be stored in the proposed facility represent a full spectrum of Department of Energy (DOE) and LLNL explosive wastes. This document identifies and evaluates the risk to human health and the environment associated with the operation of the proposed EWSF

  19. The LLNL [Lawrence Livermore National Laboratory] ICF [Inertial Confinement Fusion] Program: Progress toward ignition in the Laboratory

    International Nuclear Information System (INIS)

    Storm, E.; Batha, S.H.; Bernat, T.P.; Bibeau, C.; Cable, M.D.; Caird, J.A.; Campbell, E.M.; Campbell, J.H.; Coleman, L.W.; Cook, R.C.; Correll, D.L.; Darrow, C.B.; Davis, J.I.; Drake, R.P.; Ehrlich, R.B.; Ellis, R.J.; Glendinning, S.G.; Haan, S.W.; Haendler, B.L.; Hatcher, C.W.; Hatchett, S.P.; Hermes, G.L.; Hunt, J.P.; Kania, D.R.; Kauffman, R.L.; Kilkenny, J.D.; Kornblum, H.N.; Kruer, W.L.; Kyrazis, D.T.; Lane, S.M.; Laumann, C.W.; Lerche, R.A.; Letts, S.A.; Lindl, J.D.; Lowdermilk, W.H.; Mauger, G.J.; Montgomery, D.S.; Munro, D.H.; Murray, J.R.; Phillion, D.W.; Powell, H.T.; Remington, B.R.; Ress, D.B.; Speck, D.R.; Suter, L.J.; Tietbohl, G.L.; Thiessen, A.R.; Trebes, J.E.; Trenholme, J.B.; Turner, R.E.; Upadhye, R.S.; Wallace, R.J.; Wiedwald, J.D.; Woodworth, J.G.; Young, P.M.; Ze, F.

    1990-01-01

    The Inertial Confinement Fusion (ICF) Program at the Lawrence Livermore National Laboratory (LLNL) has made substantial progress in target physics, target diagnostics, and laser science and technology. In each area, progress required the development of experimental techniques and computational modeling. The objectives of the target physics experiments in the Nova laser facility are to address and understand critical physics issues that determine the conditions required to achieve ignition and gain in an ICF capsule. The LLNL experimental program primarily addresses indirect-drive implosions, in which the capsule is driven by x rays produced by the interaction of the laser light with a high-Z plasma. Experiments address both the physics of generating the radiation environment in a laser-driven hohlraum and the physics associated with imploding ICF capsules to ignition and high-gain conditions in the absence of alpha deposition. Recent experiments and modeling have established much of the physics necessary to validate the basic concept of ignition and ICF target gain in the laboratory. The rapid progress made in the past several years, and in particular, recent results showing higher radiation drive temperatures and implosion velocities than previously obtained and assumed for high-gain target designs, has led LLNL to propose an upgrade of the Nova laser to 1.5 to 2 MJ (at 0.35 μm) to demonstrate ignition and energy gains of 10 to 20 -- the Nova Upgrade

  20. Separation of CsCl and SrCl_2 from a ternary CsCl-SrCl_2-LiCl via a zone refining process for waste salt minimization of pyroprocessing

    International Nuclear Information System (INIS)

    Shim, Moonsoo; Choi, Ho Gil; Yi, Kyung Woo; Hwang, Il Soon; Lee, Jong Hyeon

    2016-01-01

    The purification of LiCl salt mixture has traditionally been carried out by a melt crystallization process. To improve the throughput of zone refining, three heaters were installed in the zone refiner. The zone refining method was used to grow pure LiCl salt ingots from LiCl-CsCl-SrCl_2 salt mixture. The main investigated parameters were the heater speed and the number of passes. A change in the LiCl crystal grain size was observed according to the horizontal direction. From each zone refined salt ingot, samples were collected horizontally. To analyze the concentrations of Sr and Cs, an inductively coupled plasma optical emission spectrometer and inductively coupled plasma mass spectrometer were used, respectively. The experimental results show that Sr and Cs concentrations at the initial region of the ingot were low and reached their peak at the final freezing region of the salt ingot. Concentration results of zone refined salt were compared with theoretical results yielded by the proposed model to validate its predictions. The k_e_f_f of Sr and Cs were 0.13 and 0.11, respectively. The decontamination factors of Sr and Cs were 450 and 1650, respectively. - Highlights: • The LiCl-CsCl-SrCl_2 salt ingot was purified by zone refining technique to minimize waste salt. • The concentration distribution of Cs and Sr were analyzed by mass transfer equation. • The decontamination factors of Cs and Sr were 1600 and 450 respectively in case of 60% of recovery yield.

  1. Separation of CsCl and SrCl{sub 2} from a ternary CsCl-SrCl{sub 2}-LiCl via a zone refining process for waste salt minimization of pyroprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Moonsoo [Graduate School of Energy Science and Technology, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Choi, Ho Gil; Yi, Kyung Woo; Hwang, Il Soon [Graduate School of Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826 (Korea, Republic of); Lee, Jong Hyeon, E-mail: jonglee@cnu.ac.kr [Graduate School of Energy Science and Technology, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Graduate School of Department of Advanced Materials Engineering, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Rapid Solidified Materials Research Center, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of)

    2016-11-15

    The purification of LiCl salt mixture has traditionally been carried out by a melt crystallization process. To improve the throughput of zone refining, three heaters were installed in the zone refiner. The zone refining method was used to grow pure LiCl salt ingots from LiCl-CsCl-SrCl{sub 2} salt mixture. The main investigated parameters were the heater speed and the number of passes. A change in the LiCl crystal grain size was observed according to the horizontal direction. From each zone refined salt ingot, samples were collected horizontally. To analyze the concentrations of Sr and Cs, an inductively coupled plasma optical emission spectrometer and inductively coupled plasma mass spectrometer were used, respectively. The experimental results show that Sr and Cs concentrations at the initial region of the ingot were low and reached their peak at the final freezing region of the salt ingot. Concentration results of zone refined salt were compared with theoretical results yielded by the proposed model to validate its predictions. The k{sub eff} of Sr and Cs were 0.13 and 0.11, respectively. The decontamination factors of Sr and Cs were 450 and 1650, respectively. - Highlights: • The LiCl-CsCl-SrCl{sub 2} salt ingot was purified by zone refining technique to minimize waste salt. • The concentration distribution of Cs and Sr were analyzed by mass transfer equation. • The decontamination factors of Cs and Sr were 1600 and 450 respectively in case of 60% of recovery yield.

  2. WasteWise Resource Management: Innovative Solid Waste Contracting Methods

    Science.gov (United States)

    Resource management is an innovative contractual partnership between a waste-generating organization and a qualified contractor that changes the nature of current disposal services to support waste minimization and recycling.

  3. Design of a nuclear-waste package for emplacement in tuff

    International Nuclear Information System (INIS)

    O'Neal, W.C.; Rothman, A.J.; Gregg, D.W.; Hockman, J.N.; Revelli, M.A.; Russell, E.W.; Schornhorst, J.R.

    1983-01-01

    Design, modeling, and testing activities are under way at LLNL in the development of high level nuclear waste package designs. We discuss the geological characteristics affecting design, the 10CFR60 design requirements, conceptual designs, metals for containment barriers, economic analysis, thermal modeling, and performance modeling

  4. Strengthening LLNL Missions through Laboratory Directed Research and Development in High Performance Computing

    Energy Technology Data Exchange (ETDEWEB)

    Willis, D. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-12-01

    High performance computing (HPC) has been a defining strength of Lawrence Livermore National Laboratory (LLNL) since its founding. Livermore scientists have designed and used some of the world’s most powerful computers to drive breakthroughs in nearly every mission area. Today, the Laboratory is recognized as a world leader in the application of HPC to complex science, technology, and engineering challenges. Most importantly, HPC has been integral to the National Nuclear Security Administration’s (NNSA’s) Stockpile Stewardship Program—designed to ensure the safety, security, and reliability of our nuclear deterrent without nuclear testing. A critical factor behind Lawrence Livermore’s preeminence in HPC is the ongoing investments made by the Laboratory Directed Research and Development (LDRD) Program in cutting-edge concepts to enable efficient utilization of these powerful machines. Congress established the LDRD Program in 1991 to maintain the technical vitality of the Department of Energy (DOE) national laboratories. Since then, LDRD has been, and continues to be, an essential tool for exploring anticipated needs that lie beyond the planning horizon of our programs and for attracting the next generation of talented visionaries. Through LDRD, Livermore researchers can examine future challenges, propose and explore innovative solutions, and deliver creative approaches to support our missions. The present scientific and technical strengths of the Laboratory are, in large part, a product of past LDRD investments in HPC. Here, we provide seven examples of LDRD projects from the past decade that have played a critical role in building LLNL’s HPC, computer science, mathematics, and data science research capabilities, and describe how they have impacted LLNL’s mission.

  5. LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    International Nuclear Information System (INIS)

    O'Connor, D.G.; Fisher, S.E.; Holdaway, R.

    1998-08-01

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program's preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO 2 and UO 2 ), typically containing 95% or more UO 2 . DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO 2 powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO 2 powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required

  6. Attenuation Drift in the Micro-Computed Tomography System at LLNL

    Energy Technology Data Exchange (ETDEWEB)

    Dooraghi, Alex A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Brown, William [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Seetho, Isaac [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kallman, Jeff [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lennox, Kristin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Glascoe, Lee [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-01-12

    The maximum allowable level of drift in the linear attenuation coefficients (μ) for a Lawrence Livermore National Laboratory (LLNL) micro-computed tomography (MCT) system was determined to be 0.1%. After ~100 scans were acquired during the period of November 2014 to March 2015, the drift in μ for a set of six reference materials reached or exceeded 0.1%. Two strategies have been identified to account for or correct the drift. First, normalizing the 160 kV and 100 kV μ data by the μ of water at the corresponding energy, in contrast to conducting normalization at the 160 kV energy only, significantly compensates for measurement drift. Even after the modified normalization, μ of polytetrafluoroethylene (PTFE) increases linearly with scan number at an average rate of 0.00147% per scan. This is consistent with PTFE radiation damage documented in the literature. The second strategy suggested is the replacement of the PTFE reference with fluorinated ethylene propylene (FEP), which has the same effective atomic number (Ze) and electron density (ρe) as PTFE, but is 10 times more radiation resistant. This is important as effective atomic number and electron density are key parameters in analysis. The presence of a material with properties such as PTFE, when taken together with the remaining references, allows for a broad range of the (Ze, ρe) feature space to be used in analysis. While FEP is documented as 10 times more radiation resistant, testing will be necessary to assess how often, if necessary, FEP will need to be replaced. As radiation damage to references has been observed, it will be necessary to monitor all reference materials for radiation damage to ensure consistent x-ray characteristics of the references.

  7. LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1998-08-01

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

  8. 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.

  9. Nuclear waste

    International Nuclear Information System (INIS)

    1989-01-01

    This paper reviews the Department of Energy's management of underground single-shell waste storage tanks at its Hanford, Washington, site. The tanks contain highly radioactive and nonradioactive hazardous liquid and solid wastes from nuclear materials production. Hundreds of thousands of gallons of these wastes have leaked, contaminating the soil, and a small amount of leaked waste has reached the groundwater. DOE does not collect sufficient data to adequately trace the migration of the leaks through the soil, and studies predicting the eventual environmental impact of tank leaks do not provide convincing support for DOE's conclusion that the impact will be low or nonexistent. DOE can do more to minimize the environmental risks associated with leaks. To reduce the environmental impact of past leaks, DOE may be able to install better ground covering over the tanks to reduce the volume of precipitation that drains through the soil and carries contaminants toward groundwater

  10. Recycling - Danish Waste Management Strategy

    DEFF Research Database (Denmark)

    Romann, Anne Funch; Thøgersen, John; Husmer, Lis

    The report challanges recycling as the only waste handling strategy. The tonnes of recycled materials should not be the only goal - it is essential to minimize the waste production and focus on eliminating hazardous materials.......The report challanges recycling as the only waste handling strategy. The tonnes of recycled materials should not be the only goal - it is essential to minimize the waste production and focus on eliminating hazardous materials....

  11. Predisposal Radioactive Waste Management

    International Nuclear Information System (INIS)

    2014-01-01

    Recognition of the importance of the safe management of radioactive waste means that, over the years, many well-established and effective techniques have been developed, and the nuclear industry and governments have gained considerable experience in this field. Minimization of waste is a fundamental principle underpinning the design and operation of all nuclear operations, together with waste reuse and recycling. For the remaining radioactive waste that will be produced, it is essential that there is a well defined plan (called a waste treatment path) to ensure the safe management and ultimately the safe disposal of radioactive waste so as to guarantee the sustainable long term deployment of nuclear technologies

  12. Waste management

    International Nuclear Information System (INIS)

    Dworschak, H.; Mannone, F.; Rocco, P.

    1995-01-01

    The presence of tritium in tritium-burning devices to be built for large scale research on thermonuclear fusion poses many problems especially in terms of occupational and environmental safety. One of these problems derives from the production of tritiated wastes in gaseous, liquid and solid forms. All these wastes need to be adequately processed and conditioned to minimize tritium releases to an acceptably low occupational and environmental level and consequently to protect workers and the public against the risks of unacceptable doses from exposure to tritium. Since all experimental thermonuclear fusion devices of the Tokomak type to be built and operated in the near future as well as all experimental activities undertaken in tritium laboratories like ETHEL will generate tritiated wastes, current strategies and practices to be applied for the routine management of these wastes need to be defined. Adequate background information is provided through an exhaustive literature survey. In this frame alternative tritiated waste management options so far investigated or currently applied to this end in Europe, USA and Canada have been assessed. The relevance of tritium in waste containing gamma-emitters, originated by the neutron activation of structural materials is assessed in relation to potential final disposal options. Particular importance has been attached to the tritium retention efficiency achievable by the various waste immobilization options. 19 refs., 2 figs., 1 tab

  13. Lawrence Livermore National Laboratory low-level waste systems performance assessment

    International Nuclear Information System (INIS)

    1990-11-01

    This Low-Level Radioactive Waste (LLW) Systems Performance Assessment (PA) presents a systematic analysis of the potential risks posed by the Lawrence Livermore National Laboratory (LLNL) waste management system. Potential risks to the public and environment are compared to established performance objectives as required by DOE Order 5820.2A. The report determines the associated maximum individual committed effective dose equivalent (CEDE) to a member of the public from LLW and mixed waste. A maximum annual CEDE of 0.01 mrem could result from routine radioactive liquid effluents. A maximum annual CEDE of 0.003 mrem could result from routine radioactive gaseous effluents. No other pathways for radiation exposure of the public indicated detectable levels of exposure. The dose rate, monitoring, and waste acceptance performance objectives were found to be adequately addressed by the LLNL Program. 88 refs., 3 figs., 17 tabs

  14. Fabrication and closure development of corrosion resistant containers for Nevada's Yucca Mountain high-level nuclear waste repository

    International Nuclear Information System (INIS)

    Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

    1989-11-01

    US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 2 figs., 4 tabs

  15. Evaluation of dynamic range for LLNL streak cameras using high contrast pulsed and pulse podiatry on the Nova laser system

    International Nuclear Information System (INIS)

    Richards, J.B.; Weiland, T.L.; Prior, J.A.

    1990-01-01

    This paper reports on a standard LLNL streak camera that has been used to analyze high contrast pulses on the Nova laser facility. These pulses have a plateau at their leading edge (foot) with an amplitude which is approximately 1% of the maximum pulse height. Relying on other features of the pulses and on signal multiplexing, we were able to determine how accurately the foot amplitude was being represented by the camera. Results indicate that the useful single channel dynamic range of the instrument approaches 100:1

  16. Regularity of Minimal Surfaces

    CERN Document Server

    Dierkes, Ulrich; Tromba, Anthony J; Kuster, Albrecht

    2010-01-01

    "Regularity of Minimal Surfaces" begins with a survey of minimal surfaces with free boundaries. Following this, the basic results concerning the boundary behaviour of minimal surfaces and H-surfaces with fixed or free boundaries are studied. In particular, the asymptotic expansions at interior and boundary branch points are derived, leading to general Gauss-Bonnet formulas. Furthermore, gradient estimates and asymptotic expansions for minimal surfaces with only piecewise smooth boundaries are obtained. One of the main features of free boundary value problems for minimal surfaces is t

  17. Mixed waste management options

    International Nuclear Information System (INIS)

    Owens, C.B.; Kirner, N.P.

    1992-01-01

    Currently, limited storage and treatment capacity exists for commercial mixed waste streams. No commercial mixed waste disposal is available, and it has been estimated that if and when commercial mixed waste disposal becomes available, the costs will be high. If high disposal fees are imposed, generators may be willing to apply extraordinary treatment or regulatory approaches to properly dispose of their mixed waste. This paper explores the feasibility of several waste management scenarios and management options. Existing data on commercially generated mixed waste streams are used to identify the realm of mixed waste known to be generated. Each waste stream is evaluated from both a regulatory and technical perspective in order to convert the waste into a strictly low-level radioactive or a hazardous waste. Alternative regulatory approaches evaluated in this paper include a delisting petition) no migration petition) and a treatability variance. For each waste stream, potentially available treatment options are identified that could lead to these variances. Waste minimization methodology and storage for decay are also considered. Economic feasibility of each option is discussed broadly. Another option for mixed waste management that is being explored is the feasibility of Department of Energy (DOE) accepting commercial mixed waste for treatment, storage, and disposal. A study has been completed that analyzes DOE treatment capacity in comparison with commercial mixed waste streams. (author)

  18. Remote waste handling and feed preparation for Mixed Waste Management

    International Nuclear Information System (INIS)

    Couture, S.A.; Merrill, R.D.; Densley, P.J.

    1995-05-01

    The Mixed Waste Management Facility (MWMF) at the Lawrence Livermore National Laboratory (LLNL) will serve as a national testbed to demonstrate mature mixed waste handling and treatment technologies in a complete front-end to back-end --facility (1). Remote operations, modular processing units and telerobotics for initial waste characterization, sorting and feed preparation have been demonstrated at the bench scale and have been selected for demonstration in MWMF. The goal of the Feed Preparation design team was to design and deploy a robust system that meets the initial waste preparation flexibility and productivity needs while providing a smooth upgrade path to incorporate technology advances as they occur. The selection of telerobotics for remote handling in MWMF was made based on a number of factors -- personnel protection, waste generation, maturity, cost, flexibility and extendibility. Modular processing units were selected to enable processing flexibility and facilitate reconfiguration as new treatment processes or waste streams are brought on line for demonstration. Modularity will be achieved through standard interfaces for mechanical attachment as well as process utilities, feeds and effluents. This will facilitate reconfiguration of contaminated systems without drilling, cutting or welding of contaminated materials and with a minimum of operator contact. Modular interfaces also provide a standard connection and disconnection method that can be engineered to allow convenient remote operation

  19. [Utilizing the ultraintense JanUSP laser at LLNL]. 99-ERD-049 Final LDRD Report

    International Nuclear Information System (INIS)

    Patel, P K; Price, D F; Mackinnon, A J; Springer, P T

    2002-01-01

    Recent advances in laser and optical technologies have now enabled the current generation of high intensity, ultrashort-pulse lasers to achieve focal intensities of 10 20 -10 21 W/cm 2 in pulse durations of 100-500fs. These ultraintense laser pulses are capable of producing highly relativistic plasma states with densities, temperatures, and pressures rivaling those found in the interiors of stars and nuclear weapons. Utilizing the ultraintense 100TW JanUSP laser at LLNL we have explored the possibility of ion shock heating small micron-sized plasmas to extremely high energy densities approaching 1GJ/g on timescales of a few hundred femtoseconds. The JanUSP laser delivers 10 Joules of energy in a 100fs pulse in a near diffraction-limited beam, producing intensities on target of up to 10 21 W/cm 2 . The electric field of the laser at this intensity ionizes and accelerates electrons to relativistic MeV energies. The sudden ejection of electrons from the focal region produces tremendous electrostatic forces which in turn accelerate heavier ions to MeV energies. The predicted ion flux of 1 MJ/cm 2 is sufficient to achieve thermal equilibrium conditions at high temperature in solid density targets. Our initial experiments were carried out at the available laser contrast of 10 -7 (i.e. the contrast of the amplified spontaneous emission (ASE), and of the pre-pules produced in the regenerative amplifier). We used the nuclear photoactivation of Au-197 samples to measure the gamma production above 12MeV-corresponding to the threshold for the Au-197(y,n) reaction. Since the predominant mechanism for gamma production is through the bremsstrahlung emission of energetic electrons as they pass through the solid target we were able to infer a conversion yield of several percent of the incident laser energy into electrons with energies >12MeV. This result is consistent with the interaction of the main pulse with a large pre-formed plasma. The contrast of the laser was improved to

  20. Dielectronic Satellite Spectra of Na-like Mo Ions Benchmarked by LLNL EBIT with Application to HED Plasmas

    Science.gov (United States)

    Stafford, A.; Safronova, A. S.; Kantsyrev, V. L.; Safronova, U. I.; Petkov, E. E.; Shlyaptseva, V. V.; Childers, R.; Shrestha, I.; Beiersdorfer, P.; Hell, H.; Brown, G. V.

    2017-10-01

    Dielectronic recombination (DR) is an important process for astrophysical and laboratory high energy density (HED) plasmas and the associated satellite lines are frequently used for plasma diagnostics. In particular, K-shell DR satellite lines were studied in detail in low-Z plasmas. L-shell Na-like spectral features from Mo X-pinches considered here represent the blend of DR and inner shell satellites and motivated the detailed study of DR at the EBIT-1 electron beam ion trap at LLNL. In these experiments the beam energy was swept between 0.6 - 2.4 keV to produce resonances at certain electron beam energies. The advantages of using an electron beam ion trap to better understand atomic processes with highly ionized ions in HED Mo plasma are highlighted. This work was supported by NNSA under DOE Grant DE-NA0002954. Work at LLNL was performed under the auspices of the U.S. DOE under Contract No. DE-AC52-07NA27344.