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

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

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

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

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.

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

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

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

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

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

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

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.

Summary of Waste Calcination at INTEC

Energy Technology Data Exchange (ETDEWEB)

O' Brien, Barry Henry; Newby, Bill Joe

2000-10-01

Fluidized-bed calcination at the Idaho Nuclear Technologies and Engineering Center (INTEC, formally called the Idaho Chemical Processing Plant) has been used to solidify acidic metal nitrate fuel reprocessing and incidental wastes wastes since 1961. A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. It contains feed compositions and operating conditions for all the processing campaigns for the original Waste Calcining Facility (WCF), the New Waste Calcining Facility (NWCF) started up in 1982, and numerous small scale pilot plant tests for various feed types. This summary provides a historical record of calcination at INTEC, and will be useful for evaluating calcinability of future wastes.

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

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

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

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)

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

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.

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

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

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)

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

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.

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

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

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

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

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.

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

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

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

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.

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

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.

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.

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

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

Nuclear Waste Management Program summary document, FY 1981

Energy Technology Data Exchange (ETDEWEB)

Meyers, Sheldon

1980-03-01

The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

Nuclear Waste Management Program summary document, FY 1981

International Nuclear Information System (INIS)

1980-03-01

The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

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.

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

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.

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

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

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.

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

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.

Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

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

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

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)

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.

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

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

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

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

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

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

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

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

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

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)

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

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

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

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

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

Energy Technology Data Exchange (ETDEWEB)

Britt, Phillip F [ORNL

2015-03-01

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

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

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 ...

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...

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

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

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

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

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

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

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.

Accelerator Production of Tritium Waste Characterization and Certification Challenges

International Nuclear Information System (INIS)

Ades, M.J.; England, J.L.; Nowacki, P.L.; Hane, R.; Tempel, K.L.; Pitcher, E.; Cohen, H.S.

1998-06-01

This paper summaries the processes and methods APT used for the identification and classification of the waste streams, the characterization and certification of the waste streams, and waste minimization

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

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

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.

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.

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

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

Certification plan transuranic waste: Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

1992-06-01

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

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

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.

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 ...

Solid waste and materials systems alternatives study summary

International Nuclear Information System (INIS)

Kasper, J.R.; Smith, S.T.

1996-01-01

The Hanford Site is a 560-sq.-mi. area in southeastern Washington State owned and operated by the U.S. Department of Energy (DOE). Previous weapons program activities and recent environmental cleanup activities at the Hanford Site have resulted in an accumulation of large quantities of solid wastes and materials. Future Decontamination and Decommissioning (D ampersand D) and Environmental Remediation activities will generate additional wastes. This paper provides a summary of a recently completed analysis of the Hanford Site Solid Wastes and Materials. The analysis involved development and compilation of waste stream and material information including type, classification. location current and project volumes, and curie content. Current program plans for treatment, storage, and disposal/disposition (TSD) have also been included in this analysis

Program summary. Nuclear waste management and fuel cycle programs

International Nuclear Information System (INIS)

1982-07-01

This Program Summary Document describes the US Department of Energy (DOE) Nuclear Waste Management and Fuel Cycle Programs. Particular emphasis is given to near-term, specifically Fiscal Year (FY) 1982, activities. The overall objective of these programs will be achieved by the demonstration of: (1) safe radioactive waste management practices for storage and disposal of high-level waste and (2) advanced technologies necessary to close the nuclear fuel cycle on a schedule which would assure a healthy future for the development of nuclear power in this country

Tank waste remediation system technical baseline summary description

International Nuclear Information System (INIS)

Raymond, R.E.

1998-01-01

This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations

TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETRIEVAL AND PROCESSING

Energy Technology Data Exchange (ETDEWEB)

SAMS TL; MENDOZA RE

2010-08-11

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETREIVAL AND PROCESSING

Energy Technology Data Exchange (ETDEWEB)

SAMS TL

2010-07-07

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

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...

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...

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

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...

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Harmon, K.M.; Lakey, L.T.; Silviera, D.J.; Leigh, I.W.

1987-09-01

This report is a compilation of publicly-available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 20 nations and three international agencies that have publicized their activities in this field. The information in this document is compiled to provide summary information on radioactive waste management activities in other countries. This document indicates what is occurring in other countries with regard to strategies, activities, and facilities. This document first presents a short overview of the activities and trends for managing low- to high-level radioactive waste and spent fuel by the entities covered in this review. This is followed by information for each country for nuclear power; fuel cycle and waste management strategy/policy; highlights and major milestones; institutional considerations/organizations; nuclear fuel production; fuel recycle; spent fuel storage and transport; waste conditioning, storage and transport; surface and near-surface waste disposal; geologic waste disposal; management of uranium mine and mill wastes; decommissioning; international; and references. 406 refs

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

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

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

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

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

Technology Summary Advancing Tank Waste Retrieval And Processing

International Nuclear Information System (INIS)

Sams, T.L.; Mendoza, R.E.

2010-01-01

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them. This technology overview provides a high-level summary of technologies being investigated, developed, and deployed by WRPS to advance Hanford Site tank waste retrieval and processing. Transformational technologies are needed to complete Hanford tank waste retrieval and treatment by 12/31/2047. Hanford's underground waste storage tanks hold approximately 57 million gallons of radiochemical waste from nuclear defense production - more tank waste than any other site in the United States. In addition, the waste is uniquely complicated because it contains constituents from at least six major radiochemical processes and several lesser processes. It is intermixed and complexed more than any other waste collection known to exist in the world. The multi-faceted nature of Hanford's tank waste means that legally binding agreements in the Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement) and between the Department of Energy (DOE) and its contractors may not be met using current vitrification schedules, plans, and methods. WRPS and the DOE are developing, testing, and deploying technologies to meet the necessary commitments and complete the DOE's River Protection Project (RPP) mission within environmentally acceptable requirements. Technology solutions are outlined, along with processes and priorities for selecting and developing them. DOE's Office of Environmental Management (EM) identifies the environmental management technology needs and the activities necessary to address them. The U.S. Congress then funds these activities through EM or the DOE field offices. Finally, an array of entities that include DOE site prime contractors and

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

Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Mangement Program

International Nuclear Information System (INIS)

1983-05-01

This is the first quarterly update of Radioactive Waste Management: A Summary of State Laws and Administration. Because states have been very active on waste management issues, the whole report is being reissued in this update. It covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. The administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs and a legislative contact. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and their disposition. In general, the information in this report is accurate as of 15 April 1983

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

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

Energy Technology Data Exchange (ETDEWEB)

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

2010-02-01

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

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

1988-12-01

The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities

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...

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.

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

International Nuclear Information System (INIS)

Johnson, L.J.

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed

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

Transuranic waste form characterization and data base. Executive summary

International Nuclear Information System (INIS)

1980-01-01

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

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)

Technology Summary Advancing Tank Waste Retreival And Processing

International Nuclear Information System (INIS)

Sams, T.L.

2010-01-01

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them. Hanford's underground waste storage tanks hold approximately 57 million gallons of radiochemical waste from nuclear defense production - more tank waste than any other site in the United States. In addition, the waste is uniquely complicated since it contains constituents from at least six major radiochemical processes and several lesser processes. It is intermixed and complexed more than any other waste collection known to exist in the world. The multi-faceted nature of Hanford's tank waste means that legally binding agreements in the Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement) and between the Department of Energy (DOE) and its contractors may not be met using current vitrification schedules, plans and methods. WRPS and the DOE are therefore developing, testing, and deploying technologies to ensure that they can meet the necessary commitments and complete the DOE's River Protection Project (RPP) mission within environmentally acceptable requirements. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

Energy Technology Data Exchange (ETDEWEB)

Johnson, L.J. (comp.)

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed.

National briefing summaries: Nuclear fuel cycle and waste management

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

1988-12-01

The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities.

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...

Solid Waste Information Management System (SWIMS) data summary, fiscal year 1982

International Nuclear Information System (INIS)

Watanabe, T.

1983-06-01

The Solid Waste Information Management System (SWIMS) is a Department of Energy (DOE) information system for radioactive solid waste. This document is a summary of the FY 1982 data and the forecast data for FY 1983 reported by DOE sites. Detailed data are included in the appendices. The SWIMS data base contains data on the solid transuranic and solid low-level waste generated, buried, or stored at DOE sites. The burial and storage data include the period from site initiation through FY 1982

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.

Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary

International Nuclear Information System (INIS)

1995-01-01

This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals

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

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

Summaries of Idaho National Engineering Laboratory Radioecology and Ecology Program's waste management related studies

International Nuclear Information System (INIS)

Markham, O.D.

1985-10-01

The research summaries briefly describe studies concerning the activities of small mammals on and in waste disposal sites, revegetation of waste disposal sites, and contamination of wildlife by radionuclides and the spread of radionuclides by wildlife

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

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)

Radioactive waste management: a summary of state laws and administration

International Nuclear Information System (INIS)

1983-09-01

This is the second update of Radioactive Waste Management: A Summary of State Laws and Administration. It completely replaces the first update (15 April 1983). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. Included under the compacts is a description of what the state has done or currently plans to do, as well as the compact status of other eligible states in the region. The Administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. In a number of states, Boards of Health or similar boards are lead agencies, so they have been listed in that section. Each board's administrative agency is listed under it. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs, and a legislative contact. Many legislatures do not set a date for session adjournment, so the date listed represents a combination of information provided by the states and by the history of past sessions. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and this disposition. In general, the information in this report is accurate as of July 15, 1983

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

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

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

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

Summary of the Swedish report Waste-to-energy, an inventory and review about dioxins

Energy Technology Data Exchange (ETDEWEB)

Hagelin, A. [RVF - The Swedish Association of Waste Management (Sweden)

2002-10-01

Continuous efforts are being made to further improve waste incineration as a means of dealing with household waste and other combustible material, while also producing valuable energy. The main aims are to further reduce the already low emissions to air, and to ensure effective long-term deposition of ashes and other residues from the flue-gas treatment of the waste incineration process. In order to increase knowledge in this area, the Swedish Association of Waste Management (RVF) has taken the initiative for the biggest study to date into dioxins and waste incineration in Sweden. RVF is a trade association working within the areas of waste management and recycling. The owners of Sweden's 22 waste incineration plants are all members of RVF. The study has been carried out by engineer Nils Ahlgren, an independent consultant in energy and the environment, and Professor Stellan Marklund of the University of Umeae, who has a doctorate in dioxins and conducts research into incineration technology and environmental effects. A summary of the report of this study is presented here. The order of the text in this summary follows that of the respective sections in the main report, see below for further explanation.

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 ...

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

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

National briefing summaries: Nuclear fuel cycle and waste management

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

1991-04-01

Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy.

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

1991-04-01

Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy

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

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

Radioactive waste and recoverable material in France. Summary of the National Inventory 2006

International Nuclear Information System (INIS)

2006-01-01

Thorough knowledge is needed if the various types of radioactive waste are to be managed openly, consistently and in a safe manner. All French radioactive material users have subscribed to this process for many years. Under the terms of the French Act of Parliament of 30 December 1991, the Government commissioned the French National Agency for Radioactive Waste Management (or ANDRA) to carry out a survey of all the radioactive waste present on French Territory. Through its efforts to collect and confirm information from many sources over the years, that is mainly from statements made by waste producers and handlers, ANDRA has built up a database on existing waste and its geographical location. This constantly updated resource has been regularly circulated. At the beginning of the century the Government decided to extend the areas covered by this database, in response to the recommendations made by the National Review Board (CNE) and the Parliamentary Office for Evaluating Scientific and Technology Options (OPECST). This is how the first edition of the National Inventory, published in 2004, came about. The National Inventory of Radioactive Waste and Recoverable Material, presents a full panorama of radioactive waste that it groups into waste families that present homogenous characteristics. It describes the state of the waste that may be conditioned (that is, in its final form) or may not be conditioned (that is, has not been put through sufficient treatments to arrive at its final form) at the end of 2004. Furthermore it presents not only a statistical and geographical summary, but a predictive summary, as it provides waste quantity forecasts for 2010, 2020 and beyond. The Inventory also includes recoverable materials that contain radioactivity. They are always accounted for separately because of their special nature. The data is presented in a synthesis report. This summary is the general public version of the report. The synthesis report offers more in

Radioactive waste and recoverable material in France. Summary of the National Inventory 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Thorough knowledge is needed if the various types of radioactive waste are to be managed openly, consistently and in a safe manner. All French radioactive material users have subscribed to this process for many years. Under the terms of the French Act of Parliament of 30 December 1991, the Government commissioned the French National Agency for Radioactive Waste Management (or ANDRA) to carry out a survey of all the radioactive waste present on French Territory. Through its efforts to collect and confirm information from many sources over the years, that is mainly from statements made by waste producers and handlers, ANDRA has built up a database on existing waste and its geographical location. This constantly updated resource has been regularly circulated. At the beginning of the century the Government decided to extend the areas covered by this database, in response to the recommendations made by the National Review Board (CNE) and the Parliamentary Office for Evaluating Scientific and Technology Options (OPECST). This is how the first edition of the National Inventory, published in 2004, came about. The National Inventory of Radioactive Waste and Recoverable Material, presents a full panorama of radioactive waste that it groups into waste families that present homogenous characteristics. It describes the state of the waste that may be conditioned (that is, in its final form) or may not be conditioned (that is, has not been put through sufficient treatments to arrive at its final form) at the end of 2004. Furthermore it presents not only a statistical and geographical summary, but a predictive summary, as it provides waste quantity forecasts for 2010, 2020 and beyond. The Inventory also includes recoverable materials that contain radioactivity. They are always accounted for separately because of their special nature. The data is presented in a synthesis report. This summary is the general public version of the report. The synthesis report offers more in

DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T.A. Lee

2006-02-06

This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.

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

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

Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

International Nuclear Information System (INIS)

Anon.

1988-01-01

This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

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

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

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

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.

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

Radioactive waste management: a summary of state laws and adminstration. Revision 4

International Nuclear Information System (INIS)

1984-06-01

This is the fourth update of Radioactive Waste Management: a summary of State Laws and Administration. It completely replaces the third update (January 15, 1984). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: cover page; administrative; legislative; and applicable legislation. In general, the information in this report is accurate as of April 30, 1984

Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 6

International Nuclear Information System (INIS)

1985-12-01

This is the sixth update of ''Radioactive Waste Management: A Summary of State Laws and Administration.'' It completely replaces the fifth update (15 September 1984). The updated report covers low-level radioactive waste compacts, and the administration, the legislature and the laws related to radioactive waste management in each of the fifty states. The report is organized by low-level waste compact regions. Each section begins with a description of the low-level waste compact, followed by reports on each state within the region. There are also sections for states which have made plans to dispose of waste independently of a compact, and for those states which have not yet declared their intentions. The report on each compact is divided into four sections: Cover Page, Chair Organization, State Delegations, and Compact

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

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.

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

Summary report on the 1985 United Kingdom radioactive waste inventory

International Nuclear Information System (INIS)

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

1986-04-01

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

Managing commercial high-level radioactive waste: summary

International Nuclear Information System (INIS)

1982-04-01

This summary presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste - an issue that has been debated over the last decade and that now appears to be moving toward major congressional action. After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue. The continued lack of final isolation facilities has raised two key problems that underlie debates about radioactive waste policy. First, some question the continued use of nuclear power until it is shown that safe final isolation for the resulting wastes can and will be accomplished, and argue that the failure to develop final isolation facilities is evidence that it may be an insoluble problem. Second, because there are no reprocessing facilities or federal waste isolation facilities to accept spent fuel, existing reactors are running out of spent fuel storage space, and by 1986 some may face a risk of shutting down for some period. Most of the 72,000 metric tons of spent fuel expected to be generated by the year 2000 will still be in temporary storage at that time. While it is possible that utilities could provide all necessary additional storage at reactor sites before existing basins are filled, some supplemental storage may be needed if there are delays in their efforts

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

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

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

Environmental Impact Statement: Waste Isolation Pilot Plant (WIPP): Executive summary

International Nuclear Information System (INIS)

1980-10-01

The purpose of this document is to provide a summary of the environmental impact statement for the Waste Isolation Pilot Plant (WIPP) project. The Draft Environmental Impact Statement for the WIPP was published by the US Department of Energy (DOE) in April 1979. This document was reviewed and commented on by members of the general public, private organizations, and governmental agencies. The Final Environmental Impact Statement was subsequently published in October, 1980. This summary is designed to assist decision-maker and interested individuals in reviewing the material presented in the environmental impact statement for the WIPP project. To make this material widely available, this summary is published in both Spanish and English. Additional, more detailed information concerning the environmental and safety consequences of the WIPP project is available in the Final Environmental Impact Statement. Written comments and public hearing comments on the Draft Environmental Impact Statement are available for review. 27 refs., 4 figs., 7 tabs

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

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

Hazardous Waste Cerification Plan: Hazardous Waste Handling Facility, Lawrence Berkeley Laboratory

International Nuclear Information System (INIS)

1992-02-01

The purpose of this plan is to describe the organization and methodology for the certification of hazardous waste (HW) handled in the Lawrence Berkeley Laboratory (LBL) Hazardous Waste Handling Facility (HWHF). The plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end- product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; and executive summary of the Quality Assurance Program Plan (QAPP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. The plan provides guidance from the HWHF to waste generators, waste handlers, and the Systems Group Manager to enable them to conduct their activities and carry out their responsibilities in a manner that complies with several requirements of the Federal Resource Conservation and Resource Recovery Act (RCRA), the Federal Department of Transportation (DOT), and the State of California, Code of Regulations (CCR), Title 22

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

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

Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

International Nuclear Information System (INIS)

Hladek, K.L.

1996-01-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995

Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

Hladek, K.L.

1996-06-06

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

International Nuclear Information System (INIS)

1977-06-01

The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems

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

Preliminary technical data summary defense waste processing facility stage 2

International Nuclear Information System (INIS)

1980-12-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

EMERGING TECHNOLOGY SUMMARY: VITRIFICATION OF SOILS CONTAMINATED BY HAZARDOUS AND/OR RADIOACTIVE WASTES

Science.gov (United States)

A performance summary of an advanced multifuel-capable combustion and melting system (CMS) for the vitrification of hazardous wastes is presented. Vortex Corporation has evaluated its patented CMS for use in the remediation of soils contaminated with heavy metals and radionuclid...

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

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

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

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

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

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

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.

Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

International Nuclear Information System (INIS)

1980-09-01

This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

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)

Solid Waste Information Management System (SWIMS). Data summary, Fiscal Year 1979

International Nuclear Information System (INIS)

Batchelder, H.M.

1980-07-01

The Solid Waste Information Management System (SWIMS) maintains computerized records on a master data base. It provides a comprehensive system for cataloging and assembling data into output reports. The system summarizes the solid radioactive waste generation, disposal, and storage information throughout the Department of Energy (DOE). The SWIMS data base contains the information on the transuranic (TRU) and Low-Level Waste (LLW) generated, buried, or stored by DOE facilities. The generation data covers the period from the FY 1976 transition quarter through FY 1979. The burial and storage data includes the period from site initiation through FY 1979. This document includes the DOE Summary Reports from the SWIMS, presenting the FY 1979 data and the FY 1980 forecasts. Each report is detailed by nuclide category. The categorization allows the user to separate TRU data from LLW data, etc

Certification Plan, low-level waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

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

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

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

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.

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

Effective summary evaluators for deep nuclear waste repositories: geohydrologic response function

International Nuclear Information System (INIS)

Nelson, R.W.; Dove, F.H.

1981-03-01

Useful insight has been gained over the past four years as hydrologic system modeling has been applied to evaluate hypothetical, waste-repository sites in various geologic media. The Geohydrologic Response Functions, described in this paper, are shown to: blend extensive results of technical analysis into simple summary relationships, and to potentially help the public and decision makers to evaluate the magnitude of any loss in repository integrity

Summary statement on fundamental geochemistry needs for nuclear waste isolation

International Nuclear Information System (INIS)

Giletti, B.J.

1985-01-01

A summary of basic geochemical research needs for high-level nuclear waste isolation is given. The focus of the paper is on the transport of alkalis and alkaline earths, particularly, Sr 90 and Cs 137 . The discussion addresses: 1)diffusion kinetics of different elements in crystalline solids; 2)transport kinetics along mineral grain boundaries; 3)natural rock systems that have undergone water circulation and isotope exchange; and 4)the techniques, feasibility, and promise of experimental efforts

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.

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

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.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

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

Radioactive waste management: a summary of state laws and administration. Revision 3

International Nuclear Information System (INIS)

1984-02-01

This is the third update of Radioactive Waste Management: A Summary of State Laws and Administration. It completely replaces the second update (15 July 1983). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. Included under the compacts is a description of what the state has done or currently plans to do, as well as the compact status of other eligible states in the region. In general, the information in this report is accurate as of January 1, 1984

Defense-waste vitrification studies during FY-1981. Summary report

International Nuclear Information System (INIS)

Bjorklund, W.J.

1982-09-01

Both simulated alkaline defense wastes and simulated acidic defense wastes (formed by treating alkaline waste with formic acid) were successfully vitrified in direct liquid-fed melter experiments. The vitrification process was improved while using the formate-treated waste. Leach resistance was essentially the same. Off-gas entrainment was the primary mechanism for material exiting the melter. When formate waste was vitrified, the flow behavior of the off gas from the melter changed dramatically from an erratic surging behavior to a more quiet, even flow. Hydrogen and CO were detectable while processing formate feed; however, levels exceeding the flamability limits in air were never approached. Two types of melter operation were tested during the year, one involving boost power. Several boosting methods located within the melter plenum were tested. When lid heating was being used, water spray cooling in the off gas was required. Countercurrent spray cooling was more effective than cocurrent spray cooling. Materials of construction for the off-gas system were examined. Inconel-690 is preferred in the plenum area. Inspection of the pilot-scale melter found that corrosion of the K-3 refractory and Inconel-690 electrodes was minimal. An overheating incident occurred with the LFCM in which glass temperatures up to 1480 0 C were experienced. Lab-scale vitrification tests to study mercury behavior were also completed this year. 53 figures, 63 tables

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.

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

Low-level radioactive biomedical wastes

International Nuclear Information System (INIS)

Casarett, G.W.

A summary of the management and hazards of low-level radioactive biomedical wastes is presented. The volume, disposal methods, current problems, regulatory agencies, and possible solutions to disposal problems are discussed. The benefits derived from using radioactivity in medicine are briefly described. Potential health risks are discussed. The radioactivity in most of the radioactive biomedical waste is a small fraction of that contained naturally in the human body or in the natural environment. Benefit-risk-cost considerations are presented. The cost of managing these wastes is getting so high that a new perspective for comparison of radioactivity (facts, risks, costs, benefits and trade-offs) and alternate approaches to minimize the risk and cost and maximize the benefits is suggested

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

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

Waste paper recycling opportunities for government action. Vol. 1 summary. Final report

Energy Technology Data Exchange (ETDEWEB)

Bailey, J; Love, P

1978-01-01

This paper presents a summary of analyses of the current and expected waste paper market conditions in Canada with the objective of identifying government initiatives which could permanently increase recovery levels. Emphasis has been placed upon defining short-term, practical measures which take into account the variations in market conditions for each of the major types of secondary fiber: newsprint, fine paper, and corrugated cardboard. Demand, generation and recovery are analyzed for each of these types on a national and regional basis. The opportunities for increased recycling in each region are identified and recommendations are made regarding appropriate government actions. The principal benefits of increased waste paper reclamation and recycling are perceived as: reducing waste management costs, creating new industries, promoting the conserver ethic, conserving forest and energy resources, and reducing pollution. Includes glossary. 1 fig., 5 tabs.

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…

FFTF disposable solid waste cask

Energy Technology Data Exchange (ETDEWEB)

Thomson, J. D.; Goetsch, S. D.

1983-01-01

Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper.

FFTF disposable solid waste cask

International Nuclear Information System (INIS)

Thomson, J.D.; Goetsch, S.D.

1983-01-01

Disposal of radioactive waste from the Fast Flux Test Facility (FFTF) will utilize a Disposable Solid Waste Cask (DSWC) for the transport and burial of irradiated stainless steel and inconel materials. Retrievability coupled with the desire for minimal facilities and labor costs at the disposal site identified the need for the DSWC. Design requirements for this system were patterned after Type B packages as outlined in 10 CFR 71 with a few exceptions based on site and payload requirements. A summary of the design basis, supporting analytical methods and fabrication practices developed to deploy the DSWC is provided in this paper

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

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)

Waste characterization practices: summary paper

International Nuclear Information System (INIS)

Logan, J.A.

1987-01-01

Recent reviews of the records on disposal waste at several DOE sites have indicated that records still contain little information practical to waste management. Much of the disposed waste is identified by vague terms, i.e., general plant waste. Attached to this paper is a new waste characterization code devised by the Idaho National Engineering Laboratory to aid in waste volume reduction and stabilization. It is recommended that every facility involved in waste generation and disposal needs to be detailing its wastes to support upgrading of waste management practices. 1 table

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

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.

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

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

INEL waste reduction: summary paper

International Nuclear Information System (INIS)

Rhoades, W.A.

1987-01-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

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.

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

INFX guide: summary of US DOE plans and policies for international cooperation in the field of radioactive waste management

International Nuclear Information System (INIS)

Harmon, K.M.; Kelman, J.A.

1981-01-01

The purpose of this document is to provide, in one source, an overview and summary of major international cooperative activities such as long-term personnel exchanges, planning of complementary R and D programs, and testing programs like the one at Stripa for use by DOE and DOE contractor personnel responsible for planning such programs. The contents are as follows: waste management-general, high-level waste immobilization; transuranic wastes; low-level radioactive waste; airborne wastes; waste isolation in geologic repositories; marine disposal; spent fuel storage; transportation; uranium mill tailings; decontamination and decommissioning; and appendices which are for bilaterial waste management agreements; INFX policies and procedures, DOE contractor personnel and international agencies

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

Household Hazardous Waste Disposal Project. Summary Report. Metro Toxicant Program Report No. 1A.

Science.gov (United States)

Ridgley, Susan M.; Galvin, David V.

The Household Hazardous Waste Disposal Project was established as an interagency effort to reduce the level of toxicants entering the environment by developing a control plan for the safe disposal of small quantities of household chemicals. This summary report provides an overview of the aspects of this problem that were examined, and the steps…

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

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

Studies of transuranic waste storage under conditions expected in the Waste Isolation Pilot Plant (WIPP). Interim summary report, October 1, 1977-June 15, 1979

International Nuclear Information System (INIS)

Kosiewicz, S.T.; Barraclough, B.L.; Zerwekh, A.

1980-01-01

The major focus of the program has been on the gas generation potential of organic wastes produced by radiolytic and thermal degradation under simulated WIPP storage conditions. The effects of TRU contamination level, temperature, waste type, pressure, and exposure time on radiolysis are presented. In addition, results from preliminary experiments on processed sludge dewatering are discussed. A summary is presented here of the results of a detailed study of all retrievably stored TRU wastes present at LASL before January 1, 1978. The data indicate a gross volume for the LASL inventory of 1610 m 3 with a total weight of nearly 1.24 x 10 6 kg (1240 metric tonnes). The dominant radionuclide contents of the waste are plutonium (primarily 238 Pu) and americium

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

A Research Needs Assessment for waste plastics recycling: Volume 1, Executive summary. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

This first volume provides a summary of the entire project. The study utilized the talents of a large number of participants, including a significant number of peer reviewers from industrial companies, government agencies, and research institutes. in addition, an extensive analysis of relevant literature was carried out. In considering the attractiveness of recycling technologies that are alternatives to waste-to-energy combustion units, a systems approach was utilized. Collection of waste streams containing plastics, sortation, and reclamation of plastics and plastic mixtures, reprocessing or chemical conversion of the reclaimed polymers, and the applicability of the products to specific market segments have been analyzed in the study.

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.

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

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

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)

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 1. Summary: alternatives for the back of the LWR fuel cycle types and properties of LWR fuel cycle wastes projections of waste quantities; selected glossary

International Nuclear Information System (INIS)

1976-05-01

Volume I of the five-volume report contains executive and technical summaries of the entire report, background information of the LWR fuel cycle alternatives, descriptions of waste types, and projections of waste quantities. Overview characterizations of alternative LWR fuel cycle modes are also included

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

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

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

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

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

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.

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

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)

Summary report of a seminar on geosphere modelling requirements of deep disposal of low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Piper, D.; Paige, R.W.; Broyd, T.W.

1989-02-01

A seminar on the geosphere modelling requirements of deep disposal of low and intermediate level radioactive wastes was organised by WS Atkins Engineering Sciences as part of Her Majesty's Inspectorate of Pollution's Radioactive Waste Assessment Programme. The objectives of the seminar were to review geosphere modelling capabilities and prioritise, if possible, any requirements for model development. Summaries of the presentations and subsequent discussions are given in this report. (author)

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.

DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

Energy Technology Data Exchange (ETDEWEB)

Jing, L.; Stephansson, O. [Royal Inst. of Technology, Stockholm (Sweden). Engineering Geology; Tsang, C.F. [Lawrence Berkely National Laboratory, Berkeley, CA (United States). Earth Science Div.; Mayor, J.C. [ENRESA, Madrid (Spain); Kautzky, F. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)] (eds.)

2005-02-15

DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project

DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

International Nuclear Information System (INIS)

Jing, L.; Stephansson, O.; Kautzky, F.

2005-02-01

DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project. The

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

Conference summaries

International Nuclear Information System (INIS)

1986-01-01

This volume contains conference summaries of the international conference on radioactive waste management of the Canadian Nuclear Society. Topics of discussion include: storage and disposal; hydrogeology and geochemistry; transportation; buffers and backfill; public attitudes; tailings; site investigations and geomechanics; concrete; economics; licensing; matrix materials and container design; durability of fuel; biosphere modelling; radioactive waste processing; and, future options

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.

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.

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)

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

Data summary of municipal solid waste management alternatives. Volume 7, Appendix E -- Material recovery/material recycling technologies

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

The enthusiasm for and commitment to recycling of municipal solid wastes is based on several intuitive benefits: Conservation of landfill capacity; Conservation of non-renewable natural resources and energy sources; Minimization of the perceived potential environmental impacts of MSW combustion and landfilling; Minimization of disposal costs, both directly and through material resale credits. In this discussion, ``recycling`` refers to materials recovered from the waste stream. It excludes scrap materials that are recovered and reused during industrial manufacturing processes and prompt industrial scrap. Materials recycling is an integral part of several solid waste management options. For example, in the preparation of refuse-derived fuel (RDF), ferrous metals are typically removed from the waste stream both before and after shredding. Similarly, composting facilities, often include processes for recovering inert recyclable materials such as ferrous and nonferrous metals, glass, Plastics, and paper. While these two technologies have as their primary objectives the production of RDF and compost, respectively, the demonstrated recovery of recyclables emphasizes the inherent compatibility of recycling with these MSW management strategies. This appendix discusses several technology options with regard to separating recyclables at the source of generation, the methods available for collecting and transporting these materials to a MRF, the market requirements for post-consumer recycled materials, and the process unit operations. Mixed waste MRFs associated with mass bum plants are also presented.

1994 Solid waste forecast container volume summary

International Nuclear Information System (INIS)

Templeton, K.J.; Clary, J.L.

1994-09-01

This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company's Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m 3 of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford's past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D ampersand D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D ampersand D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers

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

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.

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)

Monitoring of covering model of the National radioactive waste repository

International Nuclear Information System (INIS)

Jezikova, M.

2009-01-01

The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

1995 Solid Waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; DeForest, T.J.; Templeton, K.J.

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford's Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford

1995 Solid Waste 30-year volume summary

Energy Technology Data Exchange (ETDEWEB)

Valero, O.J. [Westinghouse Hanford Co., Richland, WA (United States); DeForest, T.J.; Templeton, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford`s Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford.

Historical summary of the fuel and waste handling and disposition activities of the TMI-2 Information and Examination Program (1980-1988)

International Nuclear Information System (INIS)

Reno, H.W.; Schmitt, R.C.

1988-10-01

This report is a historical summary of the major activities conducted by the TMI-2 Information and Examination Program in managing fuel and special radioactive wastes resulting from the accident at the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2). The activities often required the development and use of advanced handling, processing, and/or disposal technologies for those wastes

Summary of the Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

International Nuclear Information System (INIS)

1994-01-01

This is the Summary of the Environmental Impact Statement (EIS) prepared by Atomic Energy of Canada Limited (AECL) on the concept for disposal of Canada's nuclear fuel waste. The proposed concept is a method for geological disposal, based on a system of natural and engineered barriers. The EIS provides information requested by the Environmental Assessment Panel reviewing the disposal concept and presents AECL's case for the acceptability of the concept. The introductory chapter of this Summary provides background information on several topics related to nuclear fuel waste, including current storage practices for used fuel, the need for eventual disposal of nuclear fuel waste, the options for disposal, and the reasons for Canada's focus on geological disposal. Chapter 2 describes the concept for disposal of nuclear fuel waste. Because the purpose of implementing the concept would he to protect human health and the natural environment far into the future, we discuss the long-term performance of a disposal system and present a case study of potential effects on human health and the natural environment after the closure of a disposal facility. The effects and social acceptability of disposal would depend greatly on how the concept was implemented. Chapter 3 describes AECL's proposed approach to concept implementation. We discuss how the public would be involved in implementation; activities that would be undertaken to protect human health, the natural environment, and the socio-economic environment; and a case study of the potential effects of disposal before the closure of a disposal facility. The last chapter presents AECL's Conclusion, based on more than 15 years of research and development, that implementation of the disposal concept represents a means by which Canada can safely dispose of its nuclear fuel waste. This chapter also presents AECL's recommendation that Canada progress toward disposal of its nuclear fuel waste by undertaking the first stage of concept

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

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

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

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.

Summary: special waste form lysimeters - arid program

International Nuclear Information System (INIS)

Skaggs, R.L.; Walter, M.B.

1987-01-01

The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

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

Tank Waste Transport Stability: Summaries of Hanford Slurry and Salt-Solution Studies in FY 2000

Energy Technology Data Exchange (ETDEWEB)

Welch, T.D.

2002-07-08

This report is a collection of summary articles on FY 2000 studies of slurry transport and salt-well pumping related to Hanford tank waste transfers. These studies are concerned with the stability (steady, uninterrupted flow) of tank waste transfers, a subset of the Department of Energy (DOE) Tanks Focus Area Tank (TFA) Waste Chemistry effort. This work is a collaborative effort of AEA Technology plc, the Diagnostic Instrumentation and Analysis Laboratory at Mississippi State University (DIAL-MSU), the Hemispheric Center for Environmental Technology at Florida International University (HCET-FIU), Numatec Hanford Corporation (NHC), and the Oak Ridge National Laboratory (ORNL). The purpose of this report is to provide, in a single document, an overview of these studies to help the reader identify contacts and resources for obtaining more detailed information and to help promote useful interchanges between researchers and users. Despite over 50 years of experience in transporting radioactive tank wastes to and from equipment and tanks at the Department of Energy's Hanford, Savannah River, and Oak Ridge sites, waste slurry transfer pipelines and process piping become plugged on occasion. At Hanford, several tank farm pipelines are no longer in service because of plugs. At Savannah River, solid deposits in the outlet line of the 2H evaporator have resulted in an unplanned extended downtime. Although waste transfer criteria and guidelines intended to prevent pipeline plugging are in place, they are not always adequate. To avoid pipeline plugging in the future, other factors that are not currently embodied in the transfer criteria may need to be considered. The work summarized here is being conducted to develop a better understanding of the chemical and waste flow dynamics during waste transfer. The goal is to eliminate pipeline plugs by improving analysis and engineering tools in the field that incorporate this understanding.

Summary of BNL studies regarding commercial mixed waste

International Nuclear Information System (INIS)

Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.; Piciulo, P.L.

1986-09-01

Based on BNL's study it was concluded that there are low-level radioactive wastes (LLWs) which contain chemically hazardous components. Scintillation liquids may be considered an EPA listed hazardous waste and are, therefore, potential mixed wastes. Since November 1985, no operating LLW disposal site will accept these wastes for disposal. Unless such wastes contain de minimis quantities of radionuclides, they cannot be disposed of at an EPA permitted site. Currently generators of liquid scintillation wastes can ship de minimis wastes to be burned at commercial facilities. Oil wastes may also eventually be an EPA listed waste and thus will have to be considered a potential radioactive mixed waste unless NRC establishes de minimis levels of radionuclides below which oils can be managed as hazardous wastes. Regarding wastes containing lead metal there is some question as to the extent of the hazard posed by lead disposed in a LLW burial trench. Chromium-containing wastes would have to be tested to determine whether they are potential mixed wastes. There may be other wastes that are mixed wastes; the responsibility for determining this rests with the waste generator. While management options for handling potential mixed wastes are available, there is limited regulatory guidance for generators. BNL has identified and evaluated a variety of treatment options for the management of potential radioactive mixed wastes. The findings of that study showed that application of a management option with the purpose of addressing EPA concerns can, at the same time, address stabilization and volume reduction concerns of NRC. 6 refs., 1 tab

Iodine waste form summary report (FY 2007)

International Nuclear Information System (INIS)

Krumhansl, James Lee; Nenoff, Tina Maria; McMahon, Kevin A.; Gao, Huizhen; Rajan, Ashwath Natech

2007-01-01

This new program at Sandia is focused on Iodine waste form development for GNEP cycle needs. Our research has a general theme of 'Waste Forms by Design' in which we are focused on silver loaded zeolite waste forms and related metal loaded zeolites that can be validated for chosen GNEP cycle designs. With that theme, we are interested in materials flexibility for iodine feed stream and sequestration material (in a sense, the ability to develop a universal material independent on the waste stream composition). We also are designing the flexibility to work in a variety of repository or storage scenarios. This is possible by studying the structure/property relationship of existing waste forms and optimizing them to our current needs. Furthermore, by understanding the properties of the waste and the storage forms we may be able to predict their long-term behavior and stability. Finally, we are working collaboratively with the Waste Form Development Campaign to ensure materials durability and stability testing

Level trend analysis summary report for Oak Ridge National Laboratory inactive liquid low-level waste tanks

International Nuclear Information System (INIS)

1994-09-01

Oak Ridge National Laboratory facilities have produced liquid low-level waste (LLLW) that is radioactive and/or hazardous. Storage tanks have been used to collect and store these wastes. Most of the collection system, including the tanks, is located below the ground surface. Many of the systems have been removed from service (i.e., are not inactive) but contain residual amounts of waste liquid and sludges. A plan of action has been developed by DOE to ensure that environmental impacts from the waste remaining in the inactive tanks system are minimized. The Federal Facility Agreement (FFA) does not require any type of testing or monitoring for the inactive LLLW tanks that are removed from service but does require waste characterization of tanks contents, risk characterization of tanks removed from service, and remediation of the inactive tanks and their contents. This report is form information only and is not required by the FFA. It includes a description of the methodology and results of level trend analyses for the Category D tanks listed in the FFA that currently belong to the Environmental Restoration Program

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)

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

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.

Radioactive wastes and valorizable materials in France: summary of the 2004 national inventory; Dechets radioactifs et matieres valorisables en France: resume de l'inventaire national 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The French national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. This summary document contains: 1 - general introduction; 2 - classification of radioactive wastes: the 5 main categories; 3 - origin of the wastes; 4 - processing and conditioning; 5 - inventory of existing wastes: geographical inventory, inventory per category; 6 - prospective inventory: prospective scenarios, forecasting of waste production; 7 - valorizable radioactive materials; 8 - synthesis and perspective; 9 - glossary. (J.S.)

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%.

Executive summary

International Nuclear Information System (INIS)

1981-02-01

This paper is an 'executive summary' of work undertaken to review proposals for transport, handling and emplacement of high level radioactive wastes in an underground repository, appropriate to the U.K. context, with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transportation within the repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; and costs. The paper contains a section on general conclusions and recommendations. (U.K.)

A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

International Nuclear Information System (INIS)

Butcher, B.M.

1997-08-01

A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values

A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

Energy Technology Data Exchange (ETDEWEB)

Butcher, B.M.

1997-08-01

A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values.

MIxed Waste Integrated Program (MWIP): Technology summary

International Nuclear Information System (INIS)

1994-02-01

The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE's mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel

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

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

International Nuclear Information System (INIS)

Maranville, Victoria M.; McGrath, Richard

2009-01-01

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

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.

Performance assessment of geological isolation systems for radioactive waste. Summary

International Nuclear Information System (INIS)

Cadelli, N.; Cottone, G.; Orlowski, S.; Bertozzi, G.; Girardi, F.; Saltelli, A.

1988-01-01

The report summarizes the studies undertaken in the framework of the project PAGIS of the CEC Research Programme on radioactive waste. It concerns the analysis of the safety performances on the deep disposal of vitrified high level waste in four geological options: clay, granite, salt and the sub-seabed. The report describes the selection of sites and scenarios with the corresponding data base. It outlines the methodology adopted for determining the safety level which can be achieved with an underground disposal system for HLW. Two complementary approaches have been implemented: 1) a set of deterministic calculations for evaluating the dose rates as a function of time and for analysing local sensitivity on single parameters or components of the disposal system, 2) stochastic calculations for both uncertainty and global sensitivity analyses. For each option, the report presents the most significant results, obtained from the calculations at specific sites-from both the approaches. Apart the dose rates and their expectation values, the predominant radionuclides and pathways to man are identified as well as the most sensitive parameters and phenomena. The final chapter concludes stating the feasibility of safe disposal of HLW in underground repositories. This document is one of a set of 5 reports covering a relevant project of the European Community on a nuclear safety subject having very wide interest. The five volumes are: the summary (EUR 11775-EN), the clay (EUR 11776-EN), the granite (EUR 11777-FR), the salt (EUR 11778-EN) and the sub-seabed (EUR 11779-EN)

Summary

International Nuclear Information System (INIS)

2004-01-01

The fourth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste Management and enriched fissile materials. The central theme of the workshop was ''Dealing with interests, values and knowledge in managing risk''within the Belgian context of local partnerships for the long term management of low-level, short-lived radioactive waste. The four-day workshop started with a half-day session in Brussels giving a general introduction on the Belgian context and the local partnership methodology. This was followed by community visits to three local partnerships, PaLoFF in Fleurus-Farciennes, MONA in Mol, and STOLA in Dessel. After the visits, the workshop continued with two full-day sessions in Brussels. One hundred and nineteen registered participants, representing 13 countries, attended the workshop or participated in the community visits. About two thirds were Belgian stakeholders; the remainder came from FSC member organisations. The participants included representatives of municipal governments, civil society organisations, government agencies, industrial companies, the media, and international organisations as well as private citizens, consultants and academics. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop and the community visits. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Executive Summary and also provided with this document, is a NEA Secretariat's reflection aiming to place the main lessons of the workshop into an international perspective. (author)

Waste acid detoxification and reclamation: Summary of bench-scale tests for FY 1986 and FY 1987

Energy Technology Data Exchange (ETDEWEB)

Stewart, T.L.

1987-09-01

Processes to reduce the volume, quantity, and toxicity of metal-bearing waste acid are being demonstrated at Pacific Northwest Laboratory. Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication operations, which comprise a series of metal-finishing operations. Waste process acids such as HF-HNO/sub 3/, etch solutions containing Zr as a major metal impurity, and HNO/sub 3/ strip solution containing Cu as a major metal impurity are detoxified and reclaimed by concurrently precipitating heavy metals and regenerating acid for recycle. Acid from a third waste acid stream generated from chemical milling operations will be reclaimed using distillation. This stream comprises HNO/sub 3/ and H/sub 2/SO/sub 4/ containing U as the major metal impurity. Distillation allows NO/sub 3//sup -/ to be displaced by SO/sub 4//sup -2/ in metal salts; free HNO/sub 3/ is then vaporized from the U-bearing sulfate stream. Uranium can be recovered from the sulfate stream in a downstream precipitation step. 10 refs., 15 figs., 13 tabs.

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

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

Hanford Site annual waste reduction report

International Nuclear Information System (INIS)

Nichols, D.H.

1992-03-01

The US Department of Energy (DOE), Richland Field Office (RL) has developed and implemented a Hanford Site Waste Minimization and Pollution Prevention Awareness Plan that provides overall guidance and direction on waste minimization and pollution prevention awareness to the four contractors who manage and operate the Hanford Site for the RL. Waste reduction at the RL will be accomplished by following a hierarchy of environmental protection practices. First, waste generation will be eliminated or minimized through source reduction. Second, potential waste materials that cannot be eliminated or minimized will be recycled (i.e., used, reused, or reclaimed). Third, all waste that is nevertheless generated will be treated to reduce volume, toxicity, or mobility before storage or disposal. The scope of this waste reduction program will include nonhazardous, hazardous, radioactive mixed, and radioactive wastes

Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

International Nuclear Information System (INIS)

Beeman, Gordon H.

2010-01-01

The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL's '1831' use agreement and later PNNL's '1830' prime contract with DOE in support of the WTP. In March 2001, PNNL under its '1831' use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL's support to the WTP was moved under its '1830' prime contract with DOE. Documents numbered 'PNWD-XXXX' were issued under PNNL's '1831' use agreement. Documents numbered 'PNNL-XXXX' were issued under PNNL's '1830' prime contract with DOE. The documents are sorted by fiscal year and categorized as follows: (1) Characterization; (2) HLW (High Level Waste); (3) Material Characterization; (4) Pretreatment; (5) Simulant Development; (6) Vitrification; and (7) Waste Form Qualification. This report is intended to provide a compendium of reports issued by PNWD/PNNL in support of the Waste Treatment Plant. Copies of all reports can be obtained by clicking on http://www.pnl.gov/rpp-wtp/ and downloading the .pdf file(s) to your computer.

Summary Record of the First Meeting of the Radioactive Waste Repository Metadata Management (RepMet) Initiative

International Nuclear Information System (INIS)

2014-01-01

National radioactive waste repository programmes are collecting large amounts of data to support the long-term management of their nations' radioactive wastes. The data and related records increase in number, type and quality as programmes proceed through the successive stages of repository development: pre-siting, siting, characterisation, construction, operation and finally closure. Regulatory and societal approvals are included in this sequence. Some programmes are also documenting past repository projects and facing a challenge in allowing both current and future generations to understand actions carried out in the past. Metadata allows context to be stored with data and information so that it can be located, used, updated and maintained. Metadata helps waste management organisations better utilise their data in carrying out their statutory tasks and can also help verify and demonstrate that their programmes are appropriately driven. The NEA Radioactive Waste Repository Metadata Management (RepMet) initiative aims to bring about a better understanding of the identification and administration of metadata - a key aspect of data management - to support national programmes in managing their radioactive waste repository data, information and records in a way that is both harmonised internationally and suitable for long-term management and use. This is a summary record of the 1. meeting of the RepMet initiative. The actions and decisions from this meeting were sent separately to the group after the meeting, but are also included in this document (Annex A). The list of participants is attached as well (Annex B)

1995 solid waste 30-year characteristics volume summary

International Nuclear Information System (INIS)

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

1995-10-01

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

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

DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Executive summary for Phases I,II and III

International Nuclear Information System (INIS)

Jing, L.; Stephansson, O.; Tsang, C.F.; Kautsky, F.

1996-06-01

This executive summary presents the motivation, structure, objectives, methodologies and results of the first stage of the international DECOVALEX project - DECOVALEX I (1992-1995). The acronym stands for Development of Coupled Models and their Validation against Experiment in Nuclear Waste Isolation, and the project is an international effort to develop mathematical models, numerical methods and computer codes for coupled thermo-hydro-mechanical processes in fractured rocks and buffer materials for geological isolation of spent nuclear fuel and other radioactive wastes, and validate them against laboratory and field experiments. 24 refs

Radioactive waste assessment using 'minimum waste generation' scenario - summary report March 1984

International Nuclear Information System (INIS)

Richardson, J.A.; Goodill, D.R.; Tymons, B.J.

1984-11-01

This report describes an assessment of radioactive waste management arisings from a defined nuclear power generation - Scheme 1. Scheme 1 assumes a minimum waste generation scenario with raw waste arisings from 3 main groups; (i) existing and committed commercial reactors; (ii) fuel reprocessing plants, (iii) research, industry and medicine. No decommissioning wastes are considered except for arisings from the final fuel cores from decommissioned reactors. The study uses the SIMULATION2 code which models waste material flows through the system. With a knowledge of the accumulations and average production rates of the raw wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data bases for the inventory calculations and the assumptions concerning future operation of nuclear facilities were those current in 1983. Both the inventory data and plans for the future of existing nuclear installations have been updated since these calculations were completed. Therefore the results from this assessment do not represent the most up-to-date information available. The report does, however, illustrate the methodology of assessment and indicates the type of information that can be generated. (author)

Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

International Nuclear Information System (INIS)

Christensen, E.J.; Gordon, D.E.

1983-12-01

The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

Energy Technology Data Exchange (ETDEWEB)

1987-02-01

The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base.

Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

International Nuclear Information System (INIS)

1987-02-01

The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base

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

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

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

International Nuclear Information System (INIS)

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

1991-02-01

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area during the period 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and special-case wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and makes recommendations for future efforts at waste characterization. 20 refs., 3 figs., 17 tabs

Development and testing of single-shell tank waste retrieval technologies: Milestone M-45-01 summary report

International Nuclear Information System (INIS)

Shen, E.J.

1994-08-01

This report summarizes the activities undertaken to develop single-shell tank (SST) waste retrieval technology and complete scale-model testing. Completion of these activities fulfills the commitment of Milestone M-45-01 of the Hanford Federal Facility Agreement and Consent Order (the Tri-Party Agreement). Initial activities included engineering studies that compiled and evaluated data on all known retrieval technologies. Based on selection criteria incorporating regulatory, safety, and operational issues, several technologies were selected for further evaluation and testing. The testing ranged from small-scale, bench-top evaluations of individual technologies to full-scale integrated tests of multiple subsystems operating concurrently as a system using simulated wastes. The current baseline retrieval method for SSTs is hydraulic sluicing. This method has been used successfully in the past to recover waste from SSTs. Variations of this hydraulic or ''past practice'' sluicing may be used to retrieve the waste from the majority of the SSTs. To minimize the potential for releases to the soil, arm-based retrieval systems may be used to recover waste from tanks that are known or suspected to have leaked. Both hydraulic sluicing and arm-based retrieval will be demonstrated in the first SST. Hydraulic sluicing is expected to retrieve most of the waste, and arm-based retrieval will retrieve wastes that remain after sluicing. Subsequent tanks will be retrieved by either hydraulic sluicing or arm-based methods, but not both. The method will be determined by waste characterization, tank integrity (leak status), and presence of in-tank hardware. Currently, it is assumed that approximately 75% of all SSTs will be retrieved by hydraulic sluicing and the remaining tanks by arm-based methods

Treatability study of absorbent polymer waste form for mixed waste treatment

International Nuclear Information System (INIS)

Herrmann, S. D.; Lehto, M. A.; Stewart, N. A.; Croft, A. D.; Kern, P. W.

2000-01-01

A treatability study was performed to develop and characterize an absorbent polymer waste form for application to low level (LLW) and mixed low level (MLLW) aqueous wastes at Argonne National Laboratory-West (ANL-W). In this study absorbent polymers proved effective at immobilizing aqueous liquid wastes in order to meet Land Disposal Restrictions for subsurface waste disposal. Treatment of aqueous waste with absorbent polymers provides an alternative to liquid waste solidification via high-shear mixing with clays and cements. Significant advantages of absorbent polymer use over clays and cements include ease of operations and waste volume minimization. Absorbent polymers do not require high-shear mixing as do clays and cements. Granulated absorbent polymer is poured into aqueous solutions and forms a gel which passes the paint filter test as a non-liquid. Pouring versus mixing of a solidification agent not only eliminates the need for a mixing station, but also lessens exposure to personnel and the potential for spread of contamination from treatment of radioactive wastes. Waste minimization is achieved as significantly less mass addition and volume increase is required of and results from absorbent polymer use than that of clays and cements. Operational ease and waste minimization translate into overall cost savings for LLW and MLLW treatment

2014 Zero Waste Strategic Plan Executive Summary.

Energy Technology Data Exchange (ETDEWEB)

Wrons, Ralph J.

2016-05-01

Sandia National Laboratories/New Mexico is located in Albuquerque, New Mexico, primarily on Department of Energy (DOE) permitted land on approximately 2,800 acres of Kirtland Air Force Base. There are approximately 5.5 million square feet of buildings, with a workforce of approximately 9200 personnel. Sandia National Laboratories Materials Sustainability and Pollution Prevention (MSP2) program adopted in 2008 an internal team goal for New Mexico site operations for Zero Waste to Landfill by 2025. Sandia solicited a consultant to assist in the development of a Zero Waste Strategic Plan. The Zero Waste Consultant Team selected is a partnership of SBM Management Services and Gary Liss & Associates. The scope of this Plan is non-hazardous solid waste and covers the life cycle of material purchases to the use and final disposal of the items at the end of their life cycle.

Security of Radioactive Waste

International Nuclear Information System (INIS)

Goldammer, W.

2003-01-01

Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management waste reduction workshop 4

International Nuclear Information System (INIS)

1990-03-01

The fourth of a series of waste minimization/reduction workshops was held at the Sheridan Grand Hotel in Tampa, Florida, on February 6--7, 1990. The workshops are held under the auspices of the Department of Energy's (DOE's) Office of Environmental Restoration and Waste Management. This workshop provided a forum for waste minimization/reduction planning, including waste minimization assessments. The workshops assist DOE waste-generating sites in implementing waste minimization/reduction programs, plans, and activities, thus providing for optimal waste reduction within the DOE complex. All wastes are considered within this discipline: liquid, solid, and airborne, within the categories of high-level, transuranic (TRU), low-level (LLW), hazardous, and mixed. Topics of discussion within workshops encompassed a wide range of subjects. Subjects included any method or technical activity from waste generation to disposal, such as process design or improvement, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration was also given to activities for remedial action and for decontamination and disposal. 1 tab

AVLIS production plant waste management plan

International Nuclear Information System (INIS)

1984-01-01

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

Composting of biological waste. Processes and utilisation. Summary report; Bioabfallkompostierung. Verfahren und Verwertung. Kurzfassung

Energy Technology Data Exchange (ETDEWEB)

Gronauer, A.; Claassen, N.; Ebertseder, T.; Fischer, P.; Gutser, R.; Helm, M.; Popp, L.; Schoen, H.

1997-12-31

The project investigated environmentally compatible concepts for processing and utilisation of biological waste by means of composting and spreading on agriculataural and gardening plots. The project comprised three parts: Composting techniques, applications of compost in agriculture and gardening, and applications in landscaping. This volume comprises the summaries of the three part-projects. (orig./SR) [Deutsch] Die umweltschonende Aufbereitung und Verwertung von Bioabfall durch Kompostierung und Rueckfuehrung auf landwirtschaftliche und gaertnerische Flaechen wurde untersucht. Dieses Projekt war dreigeteilt in die Bereiche der Kompostierung selbst, der Anwendung des Komposts in der Landwirtschaft und seiner Anwendung im Gartenbau sowie im Garten- und Landschaftsbau (GaLa-Bau). Die vorliegende Schrift enthaelt die Zusammenfassung der genannten drei Teilberichte. (orig./SR)

A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

International Nuclear Information System (INIS)

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

1991-08-01

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

A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL

Energy Technology Data Exchange (ETDEWEB)

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

1991-08-01

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

Radioactive wastes

International Nuclear Information System (INIS)

Devarakonda, M.S.; Melvin, J.M.

1994-01-01

This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

Waste acid detoxification and reclamation: Final Phase II report: Summary of distillation and material degradation tests for FY 1987 and FY 1988

International Nuclear Information System (INIS)

Brouns, T.M.; Stewart, T.L.

1988-11-01

The objective of the Waste Acid Detoxification and Reclamation project is to develop processes for reducing the volume, quantity, and toxicity of metal-bearing waste acids. The primary incentives for implementing these types of waste minimization processes are regulatory and economic (that is, to meet requirements in the Resource Conservation and Recovery Act and reduce the cost for treatment, storage, and disposal). Two precipitation processes and a distillation process are being developed to minimize waste from fuel fabrication operations or other metal-finishing operations conducted at US Department of Energy Defense Programs (DOE-DP) facilities. Waste process acids such as (1) HF-HNO 3 etch solutions containing Zr as a major metal impurity, and (2) HNO 3 strip solutions containing Cu as a major metal impurity are detoxified and reclaimed by concurrently precipitating heavy metals and regenerating acid for recycle. Acid from a third waste acid stream generated from chemical milling operations is reclaimed by the use of distillation. This stream comprises HNO 3 and H 2 SO 4 containing U as the major metal impurity. Distillation allows NO 3 /sup /minus// to be displaced by SO 4 /sup /minus/2/ in metal salts; free HNO 3 is then vaporized from the U-bearing sulfate stream. In a downstream precipitation step, uranium can be recovered from the sulfate stream. This report summarizes distillation tests and candidate material degradation tests conducted during FY 1987 and FY 1988

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

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.

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

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

International Nuclear Information System (INIS)

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

1995-03-01

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

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.

Conference summaries

Energy Technology Data Exchange (ETDEWEB)

Reynolds, Tim [Inta Communication Limited for European Service Network/ DG Research, Trillium House, 32 New Street, St. Neots, Cambridge PE19 1AJ (United Kingdom)

2004-07-01

The summaries were derived from presentations, interviews and discussions at the conference. The summaries are given at two levels, overall for the conference and for specific sessions as follows: 1) Overall Conference: 'A Sound Scientific Basis for Serious Decisions; 2) Sessions on EC Policy and Socio-Political Issues: 'Promoting Safety and Protecting Society'; 3) Session on P and T: 'Partitioning and Transmutation: A Technical Fix or Technical Training?'; 4) Sessions on Geological Disposal and Research Networking: 'No Technical Barriers to Geological Disposal'. First an overall summary of Euradwaste '04 is presented. Significant progress was made on the technical and scientific basis for geological disposal of radioactive waste during the European Commission's Fifth EURATOM Framework Programme for Research (FP5). Deep geological disposal is technically feasible now and can demonstrate the guarantees of long-term isolation and protection of the public. In parallel, socio-political studies have produced methodologies for constructive dialogue with potential host communities that reflect the honesty and openness expected by a democratic society. A harmonized legislative framework for nuclear safety and waste disposal across the enlarged European Union is currently being discussed. Disposal in deep (> 300 metre) geological repositories, the favoured strategy in Europe for long-lived high-level radioactive waste, is now possible. The Sessions on EC Policy and Socio-Political Issues are summarized as follows. The opening day of Euradwaste '04 focused on European Commission policy, including the proposed Directives on disposal of radioactive waste and nuclear safety and socio-political aspects including governance and decision making, public perception/acceptance of waste disposal and its sustainability. A decision on the proposed package will now be made after Union enlargement. Public agreement on the siting of

Sodium waste technology: A summary report

International Nuclear Information System (INIS)

Abrams, C.S.; Witbeck, L.C.

1987-01-01

The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds

Regional Management Plan: Summary report

International Nuclear Information System (INIS)

Drobny, N.L.

1986-01-01

This summary report describes the results of a 16-month project to develop a Regional Management Plan for low-level radioactive waste management in a seven-state area. The seven states are Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio, and Wisconsin. These states have formed the Midwest Interstate Low-Level Radioactive Waste Commission in accord with Congressional requirements established in 1980. 14 refs., 13 figs., 9 tabs

Waste Reduction plan for Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

Oak Ridge National Laboratory (ORNL) is a multipurpose research and development (R&D) facility owned and operated by the Department of Energy (DOE) and managed under subcontract by Martin Marietta Energy Systems (Energy Systems), Inc. ORNL R&D activities generate numerous small waste streams. In the hazardous waste category alone, over 300 streams of a diverse nature exist. Generation avoidance, reduction or recycling of wastes is an important goal in maintaining efficiency of ORNL R&D activities and protection of workers, the public, and the environment. Waste minimization is defined as any action that minimizes or eliminates the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution and inventory management, process modification, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction activities.

Waste Reduction plan for Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

Oak Ridge National Laboratory (ORNL) is a multipurpose research and development (R D) facility owned and operated by the Department of Energy (DOE) and managed under subcontract by Martin Marietta Energy Systems (Energy Systems), Inc. ORNL R D activities generate numerous small waste streams. In the hazardous waste category alone, over 300 streams of a diverse nature exist. Generation avoidance, reduction or recycling of wastes is an important goal in maintaining efficiency of ORNL R D activities and protection of workers, the public, and the environment. Waste minimization is defined as any action that minimizes or eliminates the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution and inventory management, process modification, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction activities.

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....

INC93: international nuclear congress. Technical sessions summaries

International Nuclear Information System (INIS)

Boulton, J.

1993-01-01

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged

INC93: international nuclear congress. Technical sessions summaries

Energy Technology Data Exchange (ETDEWEB)

Boulton, J

1994-12-31

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged.

Integrated solid waste management of Scottsdale, Arizona

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

The subject document reports the results of an in-depth investigation of the fiscal year 1992 cost of the city of Scottsdale, Arizona, integrated municipal solid waste management (IMSWM) system, the energy consumed to operate the system, and the environmental performance requirements for each of the system`s waste-processing and disposal facilities. The document reports actual data from records kept by participants. Every effort was made to minimize the use of assumptions, and no attempt is made to interpret the data reported. Analytical approaches are documented so that interested analysts may per-form manipulation or further analysis of the data. As such, the report is a reference document for municipal solid waste (MSW) management professionals who are interested in the actual costs and energy consumption, for a 1-year period, of an operating IMSWM system. The report is organized into two main parts. The first part is the executive summary and case study portion of the report. The executive summary provides a basic description of the study area and selected economic and energy information. Within the case study are detailed descriptions of each component operating during the study period; the quantities of solid waste collected, processed, and marketed within the study boundaries; the cost of MSW in Scottsdale; an energy usage analysis; a review of federal, state, and local environmental requirement compliance; a reference section; and a glossary of terms. The second part of the report focuses on a more detailed discourse on the above topics. In addition, the methodology used to determine the economic costs and energy consumption of the system components is found in the second portion of this report. The methodology created for this project will be helpful for those professionals who wish to break out the costs of their own integrated systems.

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

Long term performance session summary

Energy Technology Data Exchange (ETDEWEB)

Hanauer, S.

1996-05-01

This paper presents brief summaries of reports given on plutonium disposal. Topics include: performance of waste forms; glass leaching; ceramic leaching; safeguards and security issues; safeguards of vitrification; and proliferation risks of geologic disposal.

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.

Waste reduction plan for The Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Schultz, R.M.

1990-04-01

The Oak Ridge National Laboratory (ORNL) is a multipurpose Research and Development (R D) facility. These R D activities generate numerous small waste streams. Waste minimization is defined as any action that minimizes the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution, changes to processes, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction efforts. Federal regulations, DOE policies and guidelines, increased costs and liabilities associated with the management of wastes, limited disposal options and facility capacities, and public consciousness have been motivating factors for implementing comprehensive waste reduction programs. DOE Order 5820.2A, Section 3.c.2.4 requires DOE facilities to establish an auditable waste reduction program for all LLW generators. In addition, it further states that any new facilities, or changes to existing facilities, incorporate waste minimization into design considerations. A more recent DOE Order, 3400.1, Section 4.b, requires the preparation of a waste reduction program plan which must be reviewed annually and updated every three years. Implementation of a waste minimization program for hazardous and radioactive mixed wastes is sited in DOE Order 5400.3, Section 7.d.5. This document has been prepared to address these requirements. 6 refs., 1 fig., 2 tabs.

Waste reduction plan for The Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Schultz, R.M.

1990-04-01

The Oak Ridge National Laboratory (ORNL) is a multipurpose Research and Development (R ampersand D) facility. These R ampersand D activities generate numerous small waste streams. Waste minimization is defined as any action that minimizes the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution, changes to processes, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction efforts. Federal regulations, DOE policies and guidelines, increased costs and liabilities associated with the management of wastes, limited disposal options and facility capacities, and public consciousness have been motivating factors for implementing comprehensive waste reduction programs. DOE Order 5820.2A, Section 3.c.2.4 requires DOE facilities to establish an auditable waste reduction program for all LLW generators. In addition, it further states that any new facilities, or changes to existing facilities, incorporate waste minimization into design considerations. A more recent DOE Order, 3400.1, Section 4.b, requires the preparation of a waste reduction program plan which must be reviewed annually and updated every three years. Implementation of a waste minimization program for hazardous and radioactive mixed wastes is sited in DOE Order 5400.3, Section 7.d.5. This document has been prepared to address these requirements. 6 refs., 1 fig., 2 tabs

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

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

International Nuclear Information System (INIS)

2003-01-01

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

Radioactive waste disposal from Austria. Summary of experts' discussion

International Nuclear Information System (INIS)

Benischek, I.; Dincmen, T.; Ehrenstrasser, G.; Komurka, M.; Krejsa, P.; Kudlicza, P.; Schreiber, R.

1992-06-01

The aims of this report are: (1) A summary of relevant decision bases (2) A summary of comparative evaluation of ground-level and underground deposition (3) Recommendations for further investigations and on the acceptance. (authors, translated by Quittner)

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

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.

2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2008-01-01

This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R&D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R&D activities; and the maintenance program; and

2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Management

2008-01-01

This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R and D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R and D activities; and the maintenance program; and

Data summary of municipal solid waste management alternatives

Energy Technology Data Exchange (ETDEWEB)

1992-10-01

This appendix on Mass Burn Technologies is the first in a series designed to identify, describe and assess the suitability of several currently or potentially available generic technologies for the management of municipal solid waste (MSW). These appendices, which cover eight core thermoconversion, bioconversion and recycling technologies, reflect public domain information gathered from many sources. Representative sources include: professional journal articles, conference proceedings, selected municipality solid waste management plans and subscription technology data bases. The information presented is intended to serve as background information that will facilitate the preparation of the technoeconomic and life cycle mass, energy and environmental analyses that are being developed for each of the technologies. Mass burn has been and continues to be the predominant technology in Europe for the management of MSW. In the United States, the majority of the existing waste-to-energy projects utilize this technology and nearly 90 percent of all currently planned facilities have selected mass burn systems. Mass burning generally refers to the direct feeding and combustion of municipal solid waste in a furnace without any significant waste preprocessing. The only materials typically removed from the waste stream prior to combustion are large bulky objects and potentially hazardous or undesirable wastes. The technology has evolved over the last 100 or so years from simple incineration to the most highly developed and commercially proven process available for both reducing the volume of MSW and for recovering energy in the forms of steam and electricity. In general, mass burn plants are considered to operate reliably with high availability.

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.)

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

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

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

Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

1993-08-01

Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

The International hydrocoin project. Groundwater hydrology modelling strategies for performance assessment of nuclear waste disposal. Summary report

International Nuclear Information System (INIS)

1992-01-01

In 1984 the Swedish Nuclear Power Inspectorate, SKI, initiated the international cooperation project HYDROCOIN for the study of groundwater flow modelling in the context of radioactive waste disposal. The objective of HYDROCOIN was to improve knowledge of the influence of various strategies for groundwater flow modelling for the safety assessment of final repositories for radioactive wastes. The study comprised: the impact on the groundwater flow calculations of different solution algorithms, the capabilities of different models to describe field tests and bench-scale experiments, and the impact on the groundwater flow calculations of incorporating various physical phenomena. The work was conducted at three levels addressing code verification (Level 1), model validation (Level 2), and sensitivity and uncertainty analysis of groundwater flow calculations (Level 3). This report gives an overview and summary of test cases of HYDROCOIN Level 1, the issue of validation groundwater flow models (HYDROCOIN Level 2), the methodologies used in uncertainty and sensitivity analysis (HYDROCOIN Level 3). 108 figs., 24 tabs., 2 appendices

Alternative Electrochemical Salt Waste Forms, Summary of FY2010 Results

International Nuclear Information System (INIS)

Riley, Brian J.; Rieck, Bennett T.; Crum, Jarrod V.; Matyas, Josef; McCloy, John S.; Sundaram, S.K.; Vienna, John D.

2010-01-01

In FY2009, PNNL performed scoping studies to qualify two waste form candidates, tellurite (TeO2-based) glasses and halide minerals, for the electrochemical waste stream for further investigation. Both candidates showed promise with acceptable PCT release rates and effective incorporation of the 10% fission product waste stream. Both candidates received reprisal for FY2010 and were further investigated. At the beginning of FY2010, an in-depth literature review kicked off the tellurite glasses study. The review was aimed at ascertaining the state-of-the-art for chemical durability testing and mixed chloride incorporation for tellurite glasses. The literature review led the authors to 4 unique binary and 1 unique ternary systems for further investigation which include TeO2 plus the following: PbO, Al2O3-B2O3, WO3, P2O5, and ZnO. Each system was studied with and without a mixed chloride simulated electrochemical waste stream and the literature review provided the starting points for the baseline compositions as well as starting points for melting temperature, compatible crucible types, etc. The most promising glasses in each system were scaled up in production and were analyzed with the Product Consistency Test, a chemical durability test. Baseline and PCT glasses were analyzed to determine their state, i.e., amorphous, crystalline, phase separated, had undissolved material within the bulk, etc. Conclusions were made as well as the proposed direction for FY2011 plans. Sodalite was successfully synthesized by the sol-gel method. The vast majority of the dried sol-gel consisted of sodalite with small amounts of alumino-silicates and unreacted salt. Upon firing the powders made by sol-gel, the primary phase observed was sodalite with the addition of varying amounts of nepheline, carnegieite, lithium silicate, and lanthanide oxide. The amount of sodalite, nepheline, and carnegieite as well as the bulk density of the fired pellets varied with firing temperature, sol

Alternative Electrochemical Salt Waste Forms, Summary of FY2010 Results

Energy Technology Data Exchange (ETDEWEB)

Riley, Brian J.; Rieck, Bennett T.; Crum, Jarrod V.; Matyas, Josef; McCloy, John S.; Sundaram, S. K.; Vienna, John D.

2010-08-01

In FY2009, PNNL performed scoping studies to qualify two waste form candidates, tellurite (TeO2-based) glasses and halide minerals, for the electrochemical waste stream for further investigation. Both candidates showed promise with acceptable PCT release rates and effective incorporation of the 10% fission product waste stream. Both candidates received reprisal for FY2010 and were further investigated. At the beginning of FY2010, an in-depth literature review kicked off the tellurite glasses study. The review was aimed at ascertaining the state-of-the-art for chemical durability testing and mixed chloride incorporation for tellurite glasses. The literature review led the authors to 4 unique binary and 1 unique ternary systems for further investigation which include TeO2 plus the following: PbO, Al2O3-B2O3, WO3, P2O5, and ZnO. Each system was studied with and without a mixed chloride simulated electrochemical waste stream and the literature review provided the starting points for the baseline compositions as well as starting points for melting temperature, compatible crucible types, etc. The most promising glasses in each system were scaled up in production and were analyzed with the Product Consistency Test, a chemical durability test. Baseline and PCT glasses were analyzed to determine their state, i.e., amorphous, crystalline, phase separated, had undissolved material within the bulk, etc. Conclusions were made as well as the proposed direction for FY2011 plans. Sodalite was successfully synthesized by the sol-gel method. The vast majority of the dried sol-gel consisted of sodalite with small amounts of alumino-silicates and unreacted salt. Upon firing the powders made by sol-gel, the primary phase observed was sodalite with the addition of varying amounts of nepheline, carnegieite, lithium silicate, and lanthanide oxide. The amount of sodalite, nepheline, and carnegieite as well as the bulk density of the fired pellets varied with firing temperature, sol

Radioactive waste management

International Nuclear Information System (INIS)

Morley, F.

1980-01-01

A summary is given of the report of an Expert Group appointed in 1976 to consider the 1959 White Paper 'The Control of Radioactive Wastes' in the light of the changes that have taken place since it was written and with the extended remit of examining 'waste management' rather than the original 'waste disposal'. The Group undertook to; review the categories and quantities present and future of radioactive wastes, recommend the principles for the proper management of these wastes, advise whether any changes in practice or statutory controls are necessary and make recommendations. (UK)

Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

International Nuclear Information System (INIS)

Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

1993-01-01

This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

2006 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

Gregory J, Shott, Vefa Yucel

2007-03-01

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC, 2006) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, with the results submitted as an annual summary report to the U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 2000; 2002). The DOE, National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2006 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs results. This annual summary report presents data and conclusions from the FY 2006 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, and closure plans, as well as monitoring results and research and development (R&D) activities, were reviewed in FY 2006 for determination of the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed for determination of the adequacy of the CAs.

2006 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

Gregory J; Shott, Vefa Yucel

2007-01-01

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC, 2006) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, with the results submitted as an annual summary report to the U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 2000; 2002). The DOE, National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2006 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs results. This annual summary report presents data and conclusions from the FY 2006 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, and closure plans, as well as monitoring results and research and development (R and D) activities, were reviewed in FY 2006 for determination of the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed for determination of the adequacy of the CAs

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.

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.

Data Quality Objectives Summary Report for the 100-FR-1, 100-FR-2, 100-HR-1,100-KR-1, and 100-KR-2 Group 4 Waste Sites

International Nuclear Information System (INIS)

1997-10-01

The 100-FR-1, 100-FR-2, 100-HR-1, 100-KR-1, and 100-KR-2 Group 4 waste sites will be the fourth set of Hanford 100 Area sites to undergo remediation. Like the sites in Groups 1, 2,and 3, the majority of Group 4 sties are considered high priority because of the contaminants present and their proximity to the Columbia River. the data quality objectives process,summarized in this document, is a U.S. Environmental Protection Agency approach for addressing data collecting and decision-making issues that are part of an environmental remediation project. The basic cleanup assumptions made in the Group 1, 2, and 3 designs are retained for the Group 4 design. As was the case with Group 3, the most significant difference between this DQO Summary Report and the Group 1 and 2 DQO Summary Reports is the data gaps that exist for specific Group 4 waste sites. These data gaps affect the approach to waste profiling and are the principal focus of the Group 4 DQO process

Chemical analysis for waste management in paint industries

International Nuclear Information System (INIS)

Nawaz, Z.; Naveed, S.; Shiekh, N.A.; Sagheer, K.

2005-01-01

The chemical analysis of paint industries waste has been carried out; the main emission sources are the heating of raw materials and lacquer. Also the waste from other applications and production contains high concentration of heavy metals, VOC's, COD, TDS with notable acidity and alkalinity. Based on the analysis it was observed that the major losses of production could be minimized. Further toxic effects of the waste material can be minimized. In this reference measures to minimize production losses should be adopted along with the proper management. These laboratory results also lead to the areas of emissions and waste production during manufacturing process. Solutions have been proposed for process development and integrated waste minimization. (author)

A summary of available information on ferrocyanide tank wastes

International Nuclear Information System (INIS)

Burger, L.L.; Strachan, D.M.; Reynolds, D.A.; Schulz, W.W.

1991-10-01

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

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 ...

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.

Waste management for Shippingport Station Decommissioning Project: Extended summary

International Nuclear Information System (INIS)

Mullee, G.R.; Schulmeister, A.R.

1987-01-01

The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP

Solid medical waste

DEFF Research Database (Denmark)

Udofia, Emilia Asuquo; Gulis, Gabriel; Fobil, Julius

2017-01-01

BACKGROUND: Solid medical waste (SMW) in households is perceived to pose minimal risks to the public compared to SMW generated from healthcare facilities. While waste from healthcare facilities is subject to recommended safety measures to minimize risks to human health and the environment, similar...... waste in households is often untreated and co-mingled with household waste which ends up in landfills and open dumps in many African countries. In Ghana, the management of this potentially hazardous waste stream at household and community level has not been widely reported. The objective of this study...... likely to report harm in the household (OR 2.75, 95%CI 1.15-6.54). CONCLUSION: The belief that one can be harmed by diseases associated with SMW influenced reporting rates in the study area. Disposal practices suggest the presence of unwanted medicines and sharps in the household waste stream conferring...

WASTE TANK SUMMARY REPORT FOR MONTH ENDING 01/2004

International Nuclear Information System (INIS)

HANLON, B.M.

2004-01-01

This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 60 smaller miscellaneous underground storage tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of U.S. Department of Energy Order 435.1 (DOE-HQ, August 28,2001, Radioactive Waste Management, U.S. Department of Energy-Washington, D.C.) requiring the reporting of waste inventories and space utilization for the Hanford Site Tank Farm tanks

Waste Reduction Model (WARM) Resources for State and Local Government/Solid Waste Planners

Science.gov (United States)

This page provides a brief overview of how EPA’s Waste Reduction Model (WARM) can be used by state and local government/solid waste planners. The page includes a brief summary of uses of WARM for the audience and links to other resources.

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.

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

Characterization of waste streams and suspect waste from largest Los Alamos National Laboratory generators

International Nuclear Information System (INIS)

Soukup, J.D.; Erpenbeck, G.J.

1995-01-01

A detailed waste stream characterization of 4 primary generators of low level waste at LANL was performed to aid in waste minimization efforts. Data was compiled for these four generators from 1988 to the present for analyses. Prior waste minimization efforts have focused on identifying waste stream processes and performing source materials substitutions or reductions where applicable. In this historical survey, the generators surveyed included an accelerator facility, the plutonium facility, a chemistry and metallurgy research facility, and a radiochemistry research facility. Of particular interest in waste minimization efforts was the composition of suspect low level waste in which no radioactivity is detected through initial survey. Ultimately, this waste is disposed of in the LANL low level permitted waste disposal pits (thus filling a scarce and expensive resource with sanitary waste). Detailed analyses of the waste streams from these 4 facilities, have revealed that suspect low level waste comprises approximately 50% of the low level waste by volume and 47% by weight. However, there are significant differences in suspect waste density when one considers the radioactive contamination. For the 2 facilities that deal primarily with beta emitting activation and spallation products (the radiochemistry and accelerator facilities), the suspect waste is much lower density than all low level waste coming from those facilities. For the 2 facilities that perform research on transuranics (the chemistry and metallurgy research and plutonium facilities), suspect waste is higher in density than all the low level waste from those facilities. It is theorized that the low density suspect waste is composed primarily of compactable lab trash, most of which is not contaminated but can be easily surveyed. The high density waste is theorized to be contaminated with alpha emitting radionuclides, and in this case, the suspect waste demonstrates fundamental limits in detection

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)

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)

Radioactive waste management profiles. Compilation from the Waste Management Database. No. 3

International Nuclear Information System (INIS)

2000-07-01

In 1989, the International Atomic Energy Agency began development of the Waste Management Data Base (WMDB) to, primarily, establish a mechanism for the collection, archival and dissemination of information about radioactive waste management in Member States. This current report is a summary and compilation of waste management collected from Member States from February 1998 to December 1999 in response to the Agency's 1997/98 WMDB Questionnaire. Member States were asked to report waste accumulations up to the end of 1996 and to predict waste accumulations up to the end of 2014

Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1993: Report to Congress

International Nuclear Information System (INIS)

1994-06-01

This is the eighth report submitted to Congress in accordance with section 5(d)(2)(E)(ii)(II) of the Low-Level Radioactive Waste Policy Act (the Act). This section of the Act directs the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the following limitations specified in the Act: establish low-level radioactive waste disposal facilities; mitigate the impact of low-level radioactive waste disposal facilities on the host State; regulate low-level radioactive waste disposal facilities; or ensure the decommissioning, closure, and care during the period of institutional control of low-level radioactive waste disposal facilities. In addition to placing these limitations on the use of these funds, the Act also requires all nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within six months after receiving the individual reports, the Act requires the Secretary of Energy to furnish Congress with a summary of the reported expenditures and an assessment of compliance with the specified usage limitations. This report fulfills that requirement

Conference summaries

International Nuclear Information System (INIS)

1991-01-01

This volume contains conference summaries for the 31. annual conference of the Canadian Nuclear Association and the 12. annual conference of the Canadian Nuclear Society. Topics of discussion include: reactor physics; thermalhydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components, safety related computer software; nuclear fuel management; fuel behaviour and performance; reactor safety; reactor engineering; nuclear waste management; and, uranium mining and processing

2004 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

Vefa Yucel

2005-01-01

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (Bechtel Nevada, 2000) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, and reports the results in an annual summary report to the U.S. Department of Energy Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (U.S. Department of Energy [DOE]). The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2004 by evaluating operational factors and research results that impact the continuing validity of the PA and CA results. This annual summary report presents data and conclusions from the FY 2004 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, closure plans, as well as monitoring results and research and development (R and D) activities were reviewed in FY 2004 for the determination of the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed for the determination of the adequacy of the CAs

Regional Management Plan: Summary report

International Nuclear Information System (INIS)

Drobny, N.L.

1986-01-01

This summary report describes the results of a 16-month project to develop a Regional Management Plan for low-level radioactive waste management in a seven-state area. The seven states are Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio, and Wisconsin. These states have formed the Midwest Interstate Low-Level Radioactive Waste Commission in accord with Congressional requirements established in 1980. What is low-level radioactive waste? Low-level radioactive waste results from the use of radioactive materials in the treatment of disease, the production of consumer goods and industrial products, and from the generation of electricity at nuclear power plants. Low-level wastes, which are a responsibility of the states, are grouped into three classes, A, B, and C; this classification scheme is prescribed by Federal Regulations and represents different degrees of hazard associated with different concentrations of radioactive materials. Class A wastes are the least hazardous. Classes B and C represent higher hazard classes. 14 refs., 13 figs., 9 tabs

Proceedings of the US Department of Energy Office of Environmental Restoration and Waste Management: Waste reduction workshop 7

International Nuclear Information System (INIS)

1991-11-01

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

Innovative technology summary report: Innovative grouting and retrieval

International Nuclear Information System (INIS)

1998-10-01

Innovative grouting and retrieval (IGR) technology provides an innovative and cost-effective approach for full-pit and hot-spot retrieval of buried transuranic (TRU) waste sites and in situ disposal of buried waste with improved confinement. Innovative grouting technology: minimizes spreading of contamination by agglomerating the soil particles containing plutonium/americium particulates into nonaerosolizable particles; minimizes worker risks and exposure; is more effective in controlling the spread of contamination than common mining practices such as directed air flow, misting, and fixant sprays; eliminates further treatment because the grouted, rubberized waste is ready for shipment to the Waste Isolation Pilot Project (WIPP); reduces capital expenditures, operating costs, and containment structure requirements; and is an estimated five times faster than the baseline technology of removal, packaging, and storage

Technology for commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

The scope of this report is limited to technology for management of past-fission wastes produced in the commercial nuclear power light water reactor fuel cycle. Management of spent fuel (as a waste), high-level and other transuranic wastes, and gaseous wastes are characterized. Non-transuranic wastes are described, but management of these wastes, except for gaseous wastes, is excluded from the scope of this report. Volume 1 contains the summary and the bases and background information

Radioactive waste management information, 1982 summary and record-to-date

International Nuclear Information System (INIS)

Cassidy, G.B.

1983-07-01

This document summarizes radioactive waste data records for the Idaho National Engineering Laboratory (INEL) compiled since 1952. Kinds of information include volume, radioactivity, isotopic identity, origin, and decay status. The radioactive waste data presented was obtained from the INEL Radioactive Waste Management Information System (RWMIS). This report is updated annually to incorporate waste management data for the current year and reflects changes in previous annual reports. Changes are made to more accurately reflect the current status of waste operations at the INEL

Process Waste Assessment - Paint Shop

International Nuclear Information System (INIS)

Phillips, N.M.

1993-06-01

This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Paint Shop, Building 913, Room 130. Special attention is given to waste streams generated by the spray painting process because it requires a number of steps for preparing, priming, and painting an object. Also, the spray paint booth covers the largest area in R-130. The largest and most costly waste stream to dispose of is open-quote Paint Shop wasteclose quotes -- a combination of paint cans, rags, sticks, filters, and paper containers. These items are compacted in 55-gallon drums and disposed of as solid hazardous waste. Recommendations are made for minimizing waste in the Paint Shop. Paint Shop personnel are very aware of the need to minimize hazardous wastes and are continuously looking for opportunities to do so

Sustainable Waste Management for Green Highway Initiatives

Directory of Open Access Journals (Sweden)

Husin Nur Illiana

2016-01-01

Full Text Available Green highway initiative is the transportation corridors based on sustainable concept of roadway. It incorporates both transportation functionality and ecological requirements. Green highway also provides more sustainable construction technique that maximizes the lifespan of highway. Waste management is one of the sustainable criterias in the elements of green highway. Construction of highway consumes enormous amounts of waste in term of materials and energy. These wastes need to be reduce to sustain the environment. This paper aims to identify the types of waste produced from highway construction. Additionally, this study also determine the waste minimization strategy and waste management practiced.. This study main focus are construction and demolition waste only. The methodology process begin with data collection by using questionnaire survey. 22 concession companies listed under Lembaga Lebuhraya Malaysia acted as a respondent. The questionnaires were distributed to all technical department staffs. The data received was analyzed using IBM SPSS. The results shows the most production of waste is wood, soil, tree root and concrete. The least production of waste is metal. For waste minimization, the best waste minimization is reuse for all type of waste except for tree root and stump. Whereas, the best waste management is providing strategic plan. The least practice for waste management is recording the quantity of waste.