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

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

International Nuclear Information System (INIS)

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

1994-01-01

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

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

International Nuclear Information System (INIS)

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

1993-08-01

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

Waste minimization assessment procedure

International Nuclear Information System (INIS)

Kellythorne, L.L.

1993-01-01

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

Legal incentives for minimizing waste

International Nuclear Information System (INIS)

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

1991-01-01

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

Y-12 Plant waste minimization strategy

International Nuclear Information System (INIS)

Kane, M.A.

1987-01-01

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

Waste minimization handbook, Volume 1

Energy Technology Data Exchange (ETDEWEB)

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

1995-12-01

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

Waste minimization handbook, Volume 1

International Nuclear Information System (INIS)

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

1995-12-01

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

Status of LLNL granite projects

International Nuclear Information System (INIS)

Ramspott, L.D.

1980-01-01

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

Minimizing waste in environmental restoration

International Nuclear Information System (INIS)

Thuot, J.R.; Moos, L.

1996-01-01

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

Westinghouse Hanford Company waste minimization actions

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1988-09-01

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

Minimizing waste in environmental restoration

International Nuclear Information System (INIS)

Moos, L.; Thuot, J.R.

1996-01-01

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

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

International Nuclear Information System (INIS)

1995-03-01

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

Guidelines for mixed waste minimization

International Nuclear Information System (INIS)

Owens, C.

1992-02-01

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

Waste minimization at Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

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

2011-07-01

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

Waste minimization at Chalk River Laboratories

International Nuclear Information System (INIS)

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

2011-01-01

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

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

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

The development of control technologies applied to waste processing operations

International Nuclear Information System (INIS)

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

1993-02-01

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

Annual Waste Minimization Summary Report

International Nuclear Information System (INIS)

Haworth, D.M.

2011-01-01

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

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

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.

Automated system for handling tritiated mixed waste

International Nuclear Information System (INIS)

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

1995-03-01

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

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

Application of glove box robotics to hazardous waste management

International Nuclear Information System (INIS)

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

1995-02-01

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

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

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

Mixed Waste Management Facility

International Nuclear Information System (INIS)

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

1993-08-01

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

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.

Cost-benefit analysis for waste compaction alternatives at Lawrence Livermore National Laboratory: Addendum A to the Waste Minimization and Pollution Prevention Awareness Plan of May 31, 1991

International Nuclear Information System (INIS)

1992-01-01

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

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

Bronson, M.C.

1997-10-01

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

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

International Nuclear Information System (INIS)

Bronson, M.C.

1997-01-01

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

Radioactive Waste Management BasisApril 2006

Energy Technology Data Exchange (ETDEWEB)

Perkins, B K

2011-08-31

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

Using an information system to meet Hazardous Waste Management needs

International Nuclear Information System (INIS)

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

1995-02-01

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

LLNL Site 200 Risk Management Plan

International Nuclear Information System (INIS)

Pinkston, D.; Johnson, M.

2008-01-01

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

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

International Nuclear Information System (INIS)

Gonzalez, M.A.

1983-01-01

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

Radioactive Waste Management BasisSept 2001

International Nuclear Information System (INIS)

Goodwin, S.S.

2011-01-01

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

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.

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

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

Radioactive Waste Management Basis

International Nuclear Information System (INIS)

Perkins, B.K.

2009-01-01

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

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

LLNL 1981: technical horizons

International Nuclear Information System (INIS)

1981-07-01

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

2016 LLNL Nuclear Forensics Summer Program

Energy Technology Data Exchange (ETDEWEB)

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

2016-11-15

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

2016 LLNL Nuclear Forensics Summer Program

International Nuclear Information System (INIS)

Zavarin, Mavrik

2016-01-01

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

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

LLNL NESHAPs, 1993 annual report

International Nuclear Information System (INIS)

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

1994-06-01

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

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-08-11

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

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

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

2017 LLNL Nuclear Forensics Summer Internship Program

Energy Technology Data Exchange (ETDEWEB)

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

2017-12-13

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

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

Mixed waste study, Lawrence Livermore National Laboratory Hazardous Waste Management facilities

International Nuclear Information System (INIS)

1990-11-01

This document addresses the generation and storage of mixed waste at Lawrence Livermore National Laboratory (LLNL) from 1984 to 1990. Additionally, an estimate of remaining storage capacity based on the current inventory of low-level mixed waste and an approximation of current generation rates is provided. Section 2 of this study presents a narrative description of Environmental Protection Agency (EPA) and Department of Energy (DOE) requirements as they apply to mixed waste in storage at LLNL's Hazardous Waste Management (HWM) facilities. Based on information collected from the HWM non-TRU radioactive waste database, Section 3 presents a data consolidation -- by year of storage, location, LLNL generator, EPA code, and DHS code -- of the quantities of low-level mixed waste in storage. Related figures provide the distribution of mixed waste according to each of these variables. A historical review follows in Section 4. The trends in type and quantity of mixed waste managed by HWM during the past five years are delineated and graphically illustrated. Section 5 provides an estimate of remaining low-level mixed waste storage capacity at HWM. The estimate of remaining mixed waste storage capacity is based on operational storage capacity of HWM facilities and the volume of all waste currently in storage. An estimate of the time remaining to reach maximum storage capacity is based on waste generation rates inferred from the HWM database and recent HWM documents. 14 refs., 18 figs., 9 tabs

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

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

International Nuclear Information System (INIS)

Buerer, A.

1983-01-01

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

The LLNL AMS facility

International Nuclear Information System (INIS)

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

1996-05-01

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

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 ...

Annual Waste Minimization Summary Report, Calendar Year 2008

International Nuclear Information System (INIS)

2009-01-01

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

Annual Waste Minimization Summary Report, Calendar Year 2009

International Nuclear Information System (INIS)

2010-01-01

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

Annual Waste Minimization Summary Report Calendar Year 2007

International Nuclear Information System (INIS)

NSTec Environmental Management

2008-01-01

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

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

Cost-benefit analysis for waste segregation at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

1992-02-01

This report presents a cost-benefit analysis for the segregation of mixed, hazardous, and nonhazardous wastes at Lawrence Livermore National Laboratory (LLNL). The cost-benefit analysis was conducted to determine if current waste segregation practices and additional candidates for waste segregation at LLNL might have the potential for significant waste source reduction and annual savings in treatment and disposal costs. In the following cost-benefit analysis, capital costs and recurring costs of waste segregation practices are compared to the economic benefits of savings in treatment and disposal costs. Indirect or overhead costs associated with these wastes are not available and have not been included. Not considered are additional benefits of waste segregation such as decreased potential for liability to LLNL for adverse environmental effects, improved worker safety, and enhanced LLNL image within the community because of environmental improvement. The economic evaluations in this report are presented on a Lab-wide basis. All hazardous wastes generated by a program are turned over to the Hazardous Waste Management (HWM) group, which is responsible for the storage, treatment, or disposal of these wastes and funded funded directly for this work

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

LLNL/JNC repository collaboration interim progress report

International Nuclear Information System (INIS)

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

1999-01-01

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

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

FY16 LLNL Omega Experimental Programs

International Nuclear Information System (INIS)

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

2016-01-01

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

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.

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Laycak, D.T.

2010-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2008-06-16

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

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.

Laser wakefields at UCLA and LLNL

International Nuclear Information System (INIS)

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

1991-01-01

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

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

Technical Safety Requirements for the Waste Storage Facilities May 2014

Energy Technology Data Exchange (ETDEWEB)

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

2014-04-16

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Technical Safety Requirements for the Waste Storage Facilities May 2014

International Nuclear Information System (INIS)

Laycak, D. T.

2014-01-01

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Larson, H L

2007-09-07

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

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

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.

Contingency plan for the Lawrence Livermore National Laboratory's hazardous-waste operations

International Nuclear Information System (INIS)

Roberts, R.S.

1981-01-01

The Lawrence Livermore National Laboratory (LLNL) has the necessary equipment and trained personnel to respond to a large number of hazardous material spills and fires or other emergencies resulting from these spills including injured personnel. This response capability is further expanded by the agreements that LLNL has with a number of outside response agencies. The Hazards Control Department at LLNL functions as the central point for coordinating the response of the equipment and personnel. Emergencies involving hazardous waste are also coordinated through the Hazards Control Department, but the equipment and personnel in the Toxic Waste Control Group would be activated for large volume waste pumpouts. Descriptions of response equipment, hazardous waste locations communication systems, and procedures for personnel involved in the emergency are provided

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 ...

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...

The value of assessments in Lawrence Livermore National Laboratory's Waste Certification Programs

International Nuclear Information System (INIS)

Ryan, E.M.

1995-05-01

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

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Cooper, J.F.

1998-01-01

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

FY16 LLNL Omega Experimental Programs

Energy Technology Data Exchange (ETDEWEB)

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

2016-12-01

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

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...

Reuse of waste cutting sand at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Mathews, S.; Wilson, K.

1998-01-01

Lawrence Livermore National Laboratory (LLNL) examined the waste stream from a water jet cutting operation, to evaluate the possible reuse of waste garnet sand. The sand is a cutting agent used to shape a variety of materials, including metals. Nearly 70,000 pounds of waste sand is generated annually by the cutting operation. The Environmental Protection Department evaluated two potential reuses for the spent garnet sand: backfill in utility trenches; and as a concrete constituent. In both applications, garnet waste would replace the sand formerly purchased by LLNL for these purposes. Findings supported the reuse of waste garnet sand in concrete, but disqualified its proposed application as trench backfill. Waste sand stabilized in a concrete matrix appeared to present no metals-leaching hazard; however, unconsolidated sand in trenches could potentially leach metals in concentrations high enough to threaten ground water quality. A technical report submitted to the San Francisco Bay Regional Water Quality Control Board was reviewed and accepted by that body. Reuse of waste garnet cutting sand as a constituent in concrete poured to form walkways and patios at LLNL was approved

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

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

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

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2012-02-16

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

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

Federal facilities compliance act waste management

International Nuclear Information System (INIS)

Bowers, J.; Gates-Anderson, D.; Hollister, R.; Painter, S.

1999-01-01

Site Treatment Plans (STPs) developed through the Federal Facilities Compliance Act pose many technical and administrative challenges. Legacy wastes managed under these plans require Land Disposal Restriction (LDR) compliance through treatment and ultimate disposal. Although capacity has been defined for most of the Department of Energy wastes, many waste streams require further characterization and many need additional treatment and handling beyond LDR criteria to be able to dispose of the waste. At Lawrence Livermore National Laboratory (LLNL), the Hazardous Waste Management Division has developed a comprehensive Legacy Waste Program. The program directs work to manage low level and mixed wastes to ensure compliance with nuclear facility rules and its STP. This paper provides a survey of work conducted on these wastes at LLNL. They include commercial waste treatment and disposal, diverse forms of characterization, inventory maintenance and reporting, on-site treatment, and treatability studies. These activities are conducted in an integrated fashion to meet schedules defined in the STP. The processes managing wastes are dynamic due to required integration of administrative, regulatory, and technical concerns spanning the gamut to insure safe proper disposal

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.

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

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

Energy Technology Data Exchange (ETDEWEB)

Sprague, D D

2004-12-17

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

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)

Nuclear physics and heavy element research at LLNL

Energy Technology Data Exchange (ETDEWEB)

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

2009-05-11

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-05-17

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

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...

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-19

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

An assessment of potential risk resulting from a maximum credible accident scenario at the proposed explosive waste storage facility (EWSF)

International Nuclear Information System (INIS)

Otsuki, K.; Harrach, R.; Berger, R.

1992-10-01

Lawrence Livermore National Laboratory (LLNL) proposes to build, permit, and operate a storage facility for explosive wastes at LLNL's Explosive Test Site, Site 300. The facility would consist of four existing magazines, four new magazettes (small concrete vaults), and a new prefabricated metal building. Ash from on-site treatment of explosive waste would also be stored in the prefabricated metal building prior to sampling analysis, and shipment. The magazettes would be installed at each magazine-and would provide segregated storage for explosive waste types including detonators, actuators, and other initiating devices. The proposed facility would be used to store explosive wastes generated by the Hydrotest and Explosive Development Programs at LLNL prior to treatment on-site or shipment to permitted, commercial, off-site treatment facilities. Explosive wastes to be stored in the proposed facility represent a full spectrum of Department of Energy (DOE) and LLNL explosive wastes. This document identifies and evaluates the risk to human health and the environment associated with the operation of the proposed EWSF

LLNL NESHAPs 2014 Annual Report

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

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

International Nuclear Information System (INIS)

Brigdon, S.

1996-01-01

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

Applying interactive control to waste processing operations

International Nuclear Information System (INIS)

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

1992-08-01

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

Probabilistic Seismic Hazards Update for LLNL

Energy Technology Data Exchange (ETDEWEB)

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

2016-03-30

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

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

Development of positron diffraction and holography at LLNL

International Nuclear Information System (INIS)

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

2003-01-01

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

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)

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

Advanced robotics technology applied to mixed waste characterization, sorting and treatment

International Nuclear Information System (INIS)

Wilhelmsen, K.; Hurd, R.; Grasz, E.

1994-04-01

There are over one million cubic meters of radioactively contaminated hazardous waste, known as mixed waste, stored at Department of Energy facilities. Researchers at Lawrence Livermore National Laboratory (LLNL) are developing methods to safely and efficiently treat this type of waste. LLNL has automated and demonstrated a means of segregating items in a mixed waste stream. This capability incorporates robotics and automation with advanced multi-sensor information for autonomous and teleoperational handling of mixed waste items with previously unknown characteristics. The first phase of remote waste stream handling was item singulation; the ability to remove individual items of heterogeneous waste directly from a drum, box, bin, or pile. Once objects were singulated, additional multi-sensory information was used for object classification and segregation. In addition, autonomous and teleoperational surface cleaning and decontamination of homogeneous metals has been demonstrated in processing mixed waste streams. The LLNL waste stream demonstration includes advanced technology such as object classification algorithms, identification of various metal types using active and passive gamma scans and RF signatures, and improved teleoperational and autonomous grasping of waste objects. The workcell control program used an off-line programming system as a server to perform both simulation control as well as actual hardware control of the workcell. This paper will discuss the motivation for remote mixed waste stream handling, the overall workcell layout, sensor specifications, workcell supervisory control, 3D vision based automated grasp planning and object classification algorithms

Capabilities required to conduct the LLNL plutonium mission

International Nuclear Information System (INIS)

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

1991-01-01

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

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

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

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

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

Fire science at LLNL: A review

Energy Technology Data Exchange (ETDEWEB)

Hasegawa, H.K. (ed.)

1990-03-01

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

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

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

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

Energy Technology Data Exchange (ETDEWEB)

Arnold, P. M.

2013-02-21

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

Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010

International Nuclear Information System (INIS)

Hickman, D.P.; Wysong, A.R.; Heinrichs, D.P.; Wong, C.T.; Merritt, M.J.; Topper, J.D.; Gressmann, F.A.; Madden, D.J.

2011-01-01

The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE

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

Lawrence Livermore National Laboratory low-level waste systems performance assessment

International Nuclear Information System (INIS)

1990-11-01

This Low-Level Radioactive Waste (LLW) Systems Performance Assessment (PA) presents a systematic analysis of the potential risks posed by the Lawrence Livermore National Laboratory (LLNL) waste management system. Potential risks to the public and environment are compared to established performance objectives as required by DOE Order 5820.2A. The report determines the associated maximum individual committed effective dose equivalent (CEDE) to a member of the public from LLW and mixed waste. A maximum annual CEDE of 0.01 mrem could result from routine radioactive liquid effluents. A maximum annual CEDE of 0.003 mrem could result from routine radioactive gaseous effluents. No other pathways for radiation exposure of the public indicated detectable levels of exposure. The dose rate, monitoring, and waste acceptance performance objectives were found to be adequately addressed by the LLNL Program. 88 refs., 3 figs., 17 tabs

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

High intensity positron program at LLNL

International Nuclear Information System (INIS)

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

1999-01-01

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

High intensity positron program at LLNL

International Nuclear Information System (INIS)

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

1998-01-01

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

Thermochemical hydrogen production studies at LLNL: a status report

International Nuclear Information System (INIS)

Krikorian, O.H.

1982-01-01

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

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

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

GAMA-LLNL Alpine Basin Special Study: Scope of Work

Energy Technology Data Exchange (ETDEWEB)

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

2011-12-12

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

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

LLNL X-ray Calibration and Standards Laboratory

International Nuclear Information System (INIS)

Anon.

1982-01-01

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

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

LLNL NESHAPs 2015 Annual Report - June 2016

Energy Technology Data Exchange (ETDEWEB)

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

2016-06-01

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

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

LLNL high-field coil program

International Nuclear Information System (INIS)

Miller, J.R.

1986-01-01

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

LLNL pure positron plasma program

International Nuclear Information System (INIS)

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

1995-01-01

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

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

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

High intensity positron program at LLNL

International Nuclear Information System (INIS)

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

1999-01-01

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

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)

Containment barrier metals for high-level waste packages in a Tuff repository

International Nuclear Information System (INIS)

Russell, E.W.; McCright, R.D.; O'Neal, W.C.

1983-01-01

The Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package project is part of the US Department of Energy's Civilian Radioactive Waste Management (CRWM) Program. The NNWSI project is working towards the development of multibarriered packages for the disposal of spent fuel and high-level waste in tuff in the unsaturated zone at Yucca Mountain at the Nevada Test Site (NTS). The final engineered barrier system design may be composed of a waste form, canister, overpack, borehole liner, packing, and the near field host rock, or some combination thereof. Lawrence Livermore National Laboratory's (LLNL) role is to design, model, and test the waste package subsystem for the tuff repository. At the present stage of development of the nuclear waste management program at LLNL, the detailed requirements for the waste package design are not yet firmly established. In spite of these uncertainties as to the detailed package requirements, we have begun the conceptual design stage. By conceptual design, we mean design based on our best assessment of present and future regulatory requirements. We anticipate that changes will occur as the detailed requirements for waste package design are finalized. 17 references, 4 figures, 10 tables

Containment barrier metals for high-level waste packages in a Tuff repository

Energy Technology Data Exchange (ETDEWEB)

Russell, E.W.; McCright, R.D.; O`Neal, W.C.

1983-10-12

The Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package project is part of the US Department of Energy`s Civilian Radioactive Waste Management (CRWM) Program. The NNWSI project is working towards the development of multibarriered packages for the disposal of spent fuel and high-level waste in tuff in the unsaturated zone at Yucca Mountain at the Nevada Test Site (NTS). The final engineered barrier system design may be composed of a waste form, canister, overpack, borehole liner, packing, and the near field host rock, or some combination thereof. Lawrence Livermore National Laboratory`s (LLNL) role is to design, model, and test the waste package subsystem for the tuff repository. At the present stage of development of the nuclear waste management program at LLNL, the detailed requirements for the waste package design are not yet firmly established. In spite of these uncertainties as to the detailed package requirements, we have begun the conceptual design stage. By conceptual design, we mean design based on our best assessment of present and future regulatory requirements. We anticipate that changes will occur as the detailed requirements for waste package design are finalized. 17 references, 4 figures, 10 tables.

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

Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes

International Nuclear Information System (INIS)

Dominick, J.

2008-01-01

This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and

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.

LLNL Chemical Kinetics Modeling Group

Energy Technology Data Exchange (ETDEWEB)

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

2008-09-24

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

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

Sets of Reports and Articles Regarding Cement Wastes Forms Containing Alpha Emitters that are Potentially Useful for Development of Russian Federation Waste Treatment Processes for Solidification of Weapons Plutonium MOX Fuel Fabrication Wastes for

International Nuclear Information System (INIS)

Jardine, L J

2003-01-01

This is a set of nine reports and articles that were kindly provided by Dr. Christine A. Langton from the Savannah River Site (SRS) to L. J. Jardine LLNL in June 2003. The reports discuss cement waste forms and primarily focus on gas generation in cement waste forms from alpha particle decays. However other items such as various cement compositions, cement product performance test results and some cement process parameters are also included. This set of documents was put into this Lawrence Livermore National Laboratory (LLNL) releasable report for the sole purpose to provide a set of documents to Russian technical experts now beginning to study cement waste treatment processes for wastes from an excess weapons plutonium MOX fuel fabrication facility. The intent is to provide these reports for use at a US RF Experts Technical Meeting on: the Management of Wastes from MOX Fuel Fabrication Facilities, in Moscow July 9-11, 2003. The Russian experts should find these reports to be very useful for their technical and economic feasibility studies and the supporting R and D activities required to develop acceptable waste treatment processes for use in Russia as part of the ongoing Joint US RF Plutonium Disposition Activities

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.

Probabilistic Seismic Hazards Update for LLNL: PSHA Results Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-03-11

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

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

International Nuclear Information System (INIS)

Glinsky, M.E.

1994-12-01

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

LIFTERS-hyperspectral imaging at LLNL

Energy Technology Data Exchange (ETDEWEB)

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

1994-11-15

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

Selection of barrier metals for a waste package in tuff

International Nuclear Information System (INIS)

Russell, E.W.; McCright, R.D.; O'Neal, W.C.

1983-09-01

The Nevada Nuclear Waste Storage Investigation (NNWSI) project under the Civilian Radioactive Waste Management Program is planning a repository at Yucca Mountain at the Nevada Test Site for isolation of high-level nuclear waste. LLNL is developing designs for an engineered barrier system containing several barriers such as the waste form, a canister and/or an overpack, packing, and near field host rock. The selection of metal containment barriers is addressed. 13 references

Segregation and redistribution of end-of-process energetic materials

International Nuclear Information System (INIS)

McCabe, R.A.; Cummins, B.; Gonzalez, M.A.

1993-03-01

A system recovering then recycling or reusing end-of-process energetic materials has been developed at the Lawrence Livermore National Laboratory (LLNL). The system promotes separating energetic materials with high potential for reuse or recycling from those that have no further value. A feature of the system is a computerized electronic bulletin board for advertising the availability of surplus and recovered energetic materials and process chemicals to LLNL researchers, and for posting energetic materials, ''want ads.'' The system was developed and implemented to promote waste minimization and pollution prevention at LLNL

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

LLNL Mercury Project Trinity Open Science Final Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-04-20

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

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

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

Lawrence Livermore National Laboratory Decontamination and Waste Treatment Facility: Documentation of impact analysis for design alternatives presented in the Draft Environmental Impact Statement

International Nuclear Information System (INIS)

1988-05-01

Lawrence Livermore National Laboratory (LLNL) is proposing to construct and operate a new Decontamination and Waste Treatment Facility (DWTF). The proposed DWTF would replace the existing Hazardous Waste Management (HWM) facilities at LLNL. The US Department of Energy (DOE) is preparing a Draft Environmental Impact Statement (DEIS) to assess the environmental consequences of the proposed DWTF and its alternatives. This report presents the assumptions, methodologies, and analyses used to estimate the waste flows, air emissions, ambient air quality impacts, and public health risks that are presented in the DEIS. Two DWTF design alternatives (Level I and Level II) have been designated as reasonable design alternatives considering available technologies, environmental regulations, and current and future LLNL waste generation. Both design alternatives would include new, separate radioactive and nonradioactive liquid waste treatment systems, a solidification unit, a new decontamination facility, storage and treatment facilities for reactive materials, a radioactive waste storage area, receiving and classification areas, and a uranium burn pan. The Level I design alternative would include a controlled-air incinerator system, while the Level II design alternative would include a rotary kiln incinerator system. 43 refs., 4 figs., 24 tabs

Remotely controlled reagent feed system for mixed waste treatment Tank Farm

International Nuclear Information System (INIS)

Dennison, D.K.; Bowers, J.S.; Reed, R.K.

1995-02-01

LLNL has developed and installed a large-scale. remotely controlled, reagent feed system for use at its existing aqueous low-level radioactive and mixed waste treatment facility (Tank Farm). LLNL's Tank Farm is used to treat aqueous low-level and mixed wastes prior to vacuum filtration and to remove the hazardous and radioactive components before it is discharged to the City of Livermore Water Reclamation Plant (LWRP) via the sanitary sewer in accordance with established limits. This reagent feed system was installed to improve operational safety and process efficiency by eliminating the need for manual handling of various reagents used in the aqueous waste treatment processes. This was done by installing a delivery system that is controlled either remotely or locally via a programmable logic controller (PLC). The system consists of a pumping station, four sets of piping to each of six 6,800-L (1,800-gal) treatment tanks, air-actuated discharge valves at each tank, a pH/temperature probe at each tank, and the PLC-based control and monitoring system. During operation, the reagents are slowly added to the tanks in a preprogrammed and controlled manner while the pH, temperature, and liquid level are continuously monitored by the PLC. This paper presents the purpose of this reagent feed system, provides background related to LLNL's low-level/mixed waste treatment processes, describes the major system components, outlines system operation, and discusses current status and plans

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

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…

LLNL Livermore site Groundwater Surveillance Plan

International Nuclear Information System (INIS)

1992-04-01

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

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)

Hazardous waste operational plan for site 300

International Nuclear Information System (INIS)

Roberts, R.S.

1982-01-01

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

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Spill exercise 1980: an LLNL emergency training exercise

International Nuclear Information System (INIS)

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

1981-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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

Fabrication and closure development of nuclear waste containers for storage at the Yucca Mountain, Nevada repository

International Nuclear Information System (INIS)

Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

1989-04-01

US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 1 fig., 7 tabs

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

National Uranium Resource Evaluation Program: the Hydrogeochemical Stream Sediment Reconnaissance Program at LLNL

International Nuclear Information System (INIS)

Higgins, G.H.

1980-08-01

From early 1975 to mid 1979, Lawrence Livermore National Laboratory (LLNL) participated in the Hydrogeochemical Stream Sediment Reconnaissance (HSSR), part of the National Uranium Resource Evaluation (NURE) program sponsored by the Department of Energy (DOE). The Laboratory was initially responsible for collecting, analyzing, and evaluating sediment and water samples from approximately 200,000 sites in seven western states. Eventually, however, the NURE program redefined its sampling priorities, objectives, schedules, and budgets, with the increasingly obvious result that LLNL objectives and methodologies were not compatible with those of the NURE program office, and the LLNL geochemical studies were not relevant to the program goal. The LLNL portion of the HSSR program was consequently terminated, and all work was suspended by June 1979. Of the 38,000 sites sampled, 30,000 were analyzed by instrumental neutron activation analyses (INAA), delayed neutron counting (DNC), optical emission spectroscopy (OES), and automated chloride-sulfate analyses (SC). Data from about 13,000 sites have been formally reported. From each site, analyses were published of about 30 of the 60 elements observed. Uranium mineralization has been identified at several places which were previously not recognized as potential uranium source areas, and a number of other geochemical anomalies were discovered

The LLNL portable tritium processing system

International Nuclear Information System (INIS)

Anon.

1995-01-01

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

Fabrication and closure development of corrosion resistant containers for Nevada's Yucca Mountain high-level nuclear waste repository

International Nuclear Information System (INIS)

Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

1989-11-01

US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 2 figs., 4 tabs

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-08-16

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

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

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

International Nuclear Information System (INIS)

1992-09-01

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

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

Proceedings of the LLNL Technical Women`s Symposium

Energy Technology Data Exchange (ETDEWEB)

von Holtz, E. [ed.

1993-12-31

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

The LLNL Multiuser Tandem Laboratory computer-controlled radiation monitoring system

International Nuclear Information System (INIS)

Homann, S.G.

1992-01-01

The Physics Department of the Lawrence Livermore National Laboratory (LLNL) recently constructed a Multiuser Tandem Laboratory (MTL) to perform a variety of basic and applied measurement programs. The laboratory and its research equipment were constructed with support from a consortium of LLNL Divisions, Sandia National Laboratories Livermore, and the University of California. Primary design goals for the facility were inexpensive construction and operation, high beam quality at a large number of experimental stations, and versatility in adapting to new experimental needs. To accomplish these goals, our main design decisions were to place the accelerator in an unshielded structure, to make use of reconfigured cyclotrons as effective switching magnets, and to rely on computer control systems for both radiological protection and highly reproducible and well-characterized accelerator operation. This paper addresses the radiological control computer system

LLNL-G3Dv3: Global P wave tomography model for improved regional and teleseismic travel time prediction: LLNL-G3DV3---GLOBAL P WAVE TOMOGRAPHY

Energy Technology Data Exchange (ETDEWEB)

Simmons, N. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Myers, S. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Johannesson, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Matzel, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2012-10-06

[1] We develop a global-scale P wave velocity model (LLNL-G3Dv3) designed to accurately predict seismic travel times at regional and teleseismic distances simultaneously. The model provides a new image of Earth's interior, but the underlying practical purpose of the model is to provide enhanced seismic event location capabilities. The LLNL-G3Dv3 model is based on ∼2.8 millionP and Pnarrivals that are re-processed using our global multiple-event locator called Bayesloc. We construct LLNL-G3Dv3 within a spherical tessellation based framework, allowing for explicit representation of undulating and discontinuous layers including the crust and transition zone layers. Using a multiscale inversion technique, regional trends as well as fine details are captured where the data allow. LLNL-G3Dv3 exhibits large-scale structures including cratons and superplumes as well numerous complex details in the upper mantle including within the transition zone. Particularly, the model reveals new details of a vast network of subducted slabs trapped within the transition beneath much of Eurasia, including beneath the Tibetan Plateau. We demonstrate the impact of Bayesloc multiple-event location on the resulting tomographic images through comparison with images produced without the benefit of multiple-event constraints (single-event locations). We find that the multiple-event locations allow for better reconciliation of the large set of direct P phases recorded at 0–97° distance and yield a smoother and more continuous image relative to the single-event locations. Travel times predicted from a 3-D model are also found to be strongly influenced by the initial locations of the input data, even when an iterative inversion/relocation technique is employed.

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

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

International Nuclear Information System (INIS)

Daily, W.D. III

2010-01-01

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

Dispersion of Radionuclides and Exposure Assessment in Urban Environments: A Joint CEA and LLNL Report

International Nuclear Information System (INIS)

Glascoe, Lee; Gowardhan, Akshay; Lennox, Kristin; Simpson, Matthew; Yu, Kristen; Armand, Patrick; Duchenne, Christophe; Mariotte, Frederic; Pectorin, Xavier

2014-01-01

In the interest of promoting the international exchange of technical expertise, the US Department of Energy’s Office of Emergency Operations (NA-40) and the French Commissariat à l'Energie Atomique et aux énergies alternatives (CEA) requested that the National Atmospheric Release Advisory Center (NARAC) of Lawrence Livermore National Laboratory (LLNL) in Livermore, California host a joint table top exercise with experts in emergency management and atmospheric transport modeling. In this table top exercise, LLNL and CEA compared each other's flow and dispersion models. The goal of the comparison is to facilitate the exchange of knowledge, capabilities, and practices, and to demonstrate the utility of modeling dispersal at different levels of computational fidelity. Two modeling approaches were examined, a regional scale modeling approach, appropriate for simple terrain and/or very large releases, and an urban scale modeling approach, appropriate for small releases in a city environment. This report is a summary of LLNL and CEA modeling efforts from this exercise. Two different types of LLNL and CEA models were employed in the analysis: urban-scale models (Aeolus CFD at LLNL/NARAC and Parallel- Micro-SWIFT-SPRAY, PMSS, at CEA) for analysis of a 5,000 Ci radiological release and Lagrangian Particle Dispersion Models (LODI at LLNL/NARAC and PSPRAY at CEA) for analysis of a much larger (500,000 Ci) regional radiological release. Two densely-populated urban locations were chosen: Chicago with its high-rise skyline and gridded street network and Paris with its more consistent, lower building height and complex unaligned street network. Each location was considered under early summer daytime and nighttime conditions. Different levels of fidelity were chosen for each scale: (1) lower fidelity mass-consistent diagnostic, intermediate fidelity Navier-Stokes RANS models, and higher fidelity Navier-Stokes LES for urban-scale analysis, and (2) lower-fidelity single

Dispersion of Radionuclides and Exposure Assessment in Urban Environments: A Joint CEA and LLNL Report

Energy Technology Data Exchange (ETDEWEB)

Glascoe, Lee [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gowardhan, Akshay [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lennox, Kristin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Simpson, Matthew [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Yu, Kristen [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Armand, Patrick [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Duchenne, Christophe [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Mariotte, Frederic [Alternative Energies and Atomic Energy Commission (CEA), Paris (France); Pectorin, Xavier [Alternative Energies and Atomic Energy Commission (CEA), Paris (France)

2014-12-19

In the interest of promoting the international exchange of technical expertise, the US Department of Energy’s Office of Emergency Operations (NA-40) and the French Commissariat à l'Energie Atomique et aux énergies alternatives (CEA) requested that the National Atmospheric Release Advisory Center (NARAC) of Lawrence Livermore National Laboratory (LLNL) in Livermore, California host a joint table top exercise with experts in emergency management and atmospheric transport modeling. In this table top exercise, LLNL and CEA compared each other’s flow and dispersion models. The goal of the comparison is to facilitate the exchange of knowledge, capabilities, and practices, and to demonstrate the utility of modeling dispersal at different levels of computational fidelity. Two modeling approaches were examined, a regional scale modeling approach, appropriate for simple terrain and/or very large releases, and an urban scale modeling approach, appropriate for small releases in a city environment. This report is a summary of LLNL and CEA modeling efforts from this exercise. Two different types of LLNL and CEA models were employed in the analysis: urban-scale models (Aeolus CFD at LLNL/NARAC and Parallel- Micro-SWIFT-SPRAY, PMSS, at CEA) for analysis of a 5,000 Ci radiological release and Lagrangian Particle Dispersion Models (LODI at LLNL/NARAC and PSPRAY at CEA) for analysis of a much larger (500,000 Ci) regional radiological release. Two densely-populated urban locations were chosen: Chicago with its high-rise skyline and gridded street network and Paris with its more consistent, lower building height and complex unaligned street network. Each location was considered under early summer daytime and nighttime conditions. Different levels of fidelity were chosen for each scale: (1) lower fidelity mass-consistent diagnostic, intermediate fidelity Navier-Stokes RANS models, and higher fidelity Navier-Stokes LES for urban-scale analysis, and (2) lower-fidelity single

Summary of the LLNL one-dimensional transport-kinetics model of the troposphere and stratosphere: 1981

International Nuclear Information System (INIS)

Wuebbles, D.J.

1981-09-01

Since the LLNL one-dimensional coupled transport and chemical kinetics model of the troposphere and stratosphere was originally developed in 1972 (Chang et al., 1974), there have been many changes to the model's representation of atmospheric physical and chemical processes. A brief description is given of the current LLNL one-dimensional coupled transport and chemical kinetics model of the troposphere and stratosphere

Waste package materials selection process

International Nuclear Information System (INIS)

Roy, A.K.; Fish, R.L.; McCright, R.D.

1994-01-01

The office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating a site at Yucca Mountain in Southern Nevada to determine its suitability as a mined geologic disposal system (MGDS) for the disposal of high-level nuclear waste (HLW). The B ampersand W Fuel Company (BWFC), as a part of the Management and Operating (M ampersand O) team in support of the Yucca Mountain Site Characterization Project (YMP), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) is responsible for testing materials and developing models for the materials to be used in the waste package. This paper is aimed at presenting the selection process for materials needed in fabricating the different components of the waste package

Proceedings of the LLNL technical women`s symposium

Energy Technology Data Exchange (ETDEWEB)

von Holtz, E. [ed.

1994-12-31

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

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.

LLNL Contribution to LLE FY09 Annual Report: NIC and HED Results

International Nuclear Information System (INIS)

Heeter, R.F.; Landen, O.L.; Hsing, W.W.; Fournier, K.B.

2009-01-01

In FY09, LLNL led 238 target shots on the OMEGA Laser System. Approximately half of these LLNL-led shots supported the National Ignition Campaign (NIC). The remainder was dedicated to experiments for the high-energy-density stewardship experiments (HEDSE). Objectives of the LLNL led NIC campaigns at OMEGA included: (1) Laser-plasma interaction studies in physical conditions relevant for the NIF ignition targets; (2) Demonstration of Tr = 100 eV foot symmetry tuning using a reemission sphere; (3) X-ray scattering in support of conductivity measurements of solid density Be plasmas; (4) Experiments to study the physical properties (thermal conductivity) of shocked fusion fuels; (5) High-resolution measurements of velocity nonuniformities created by microscopic perturbations in NIF ablator materials; (6) Development of a novel Compton Radiography diagnostic platform for ICF experiments; and (7) Precision validation of the equation of state for quartz. The LLNL HEDSE campaigns included the following experiments: (1) Quasi-isentropic (ICE) drive used to study material properties such as strength, equation of state, phase, and phase-transition kinetics under high pressure; (2) Development of a high-energy backlighter for radiography in support of material strength experiments using Omega EP and the joint OMEGA-OMEGA-EP configuration; (3) Debris characterization from long-duration, point-apertured, point-projection x-ray backlighters for NIF radiation transport experiments; (4) Demonstration of ultrafast temperature and density measurements with x-ray Thomson scattering from short-pulse laser-heated matter; (5) The development of an experimental platform to study nonlocal thermodynamic equilibrium (NLTE) physics using direct-drive implosions; (6) Opacity studies of high-temperature plasmas under LTE conditions; and (7) Characterization of copper (Cu) foams for HEDSE experiments.

Operating characteristics and modeling of the LLNL 100-kV electric gun

International Nuclear Information System (INIS)

Osher, J.E.; Barnes, G.; Chau, H.H.; Lee, R.S.; Lee, C.; Speer, R.; Weingart, R.C.

1989-01-01

In the electric gun, the explosion of an electrically heated metal foil and the accompanying magnetic forces drive a thin flyer plate up a short barrel. Flyer velocities of up to 18 km/s make the gun useful for hypervelocity impact studies. The authors briefly review the technological evolution of the exploding-metal circuit elements that power the gun, describe the 100-kV electric gun designed at Lawrence Livermore National Laboratory (LLNL) in some detail, and present the general principles of electric gun operation. They compare the experimental performance of the LLNL gun with a simple model and with predictions of a magnetohydrodynamics code

DWTF [decontamination and waste treatment facilities] assessment

International Nuclear Information System (INIS)

Maimoni, A.

1986-01-01

The purpose of this study has been to evaluate the adequacy of present and proposed decontamination and waste treatment facilities (DWTF) at LLNL, to determine the cost effectiveness for proposed improvements, and possible alternatives for accomplishing these improvements. To the extent possible, we have also looked at some of the proposed environmental compliance and cleanup (ECC) projects

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

Design of a nuclear-waste package for emplacement in tuff

International Nuclear Information System (INIS)

O'Neal, W.C.; Rothman, A.J.; Gregg, D.W.; Hockman, J.N.; Revelli, M.A.; Russell, E.W.; Schornhorst, J.R.

1983-01-01

Design, modeling, and testing activities are under way at LLNL in the development of high level nuclear waste package designs. We discuss the geological characteristics affecting design, the 10CFR60 design requirements, conceptual designs, metals for containment barriers, economic analysis, thermal modeling, and performance modeling

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)

Waste Isolation Pilot Plant Technical Assessment Team Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2015-03-17

This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

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

Hydrogen production from municipal solid waste

Energy Technology Data Exchange (ETDEWEB)

Wallman, P.H.; Richardson, J.H.; Thorsness, C.B. [and others

1996-06-28

We have modified a Municipal Solid Waste (MSW) hydrothermal pretreatment pilot plant for batch operation and blowdown of the treated batch to low pressure. We have also assembled a slurry shearing pilot plant for particle size reduction. Waste paper and a mixture of waste paper/polyethylene plastic have been run in the pilot plant with a treatment temperature of 275{degrees}C. The pilot-plant products have been used for laboratory studies at LLNL. The hydrothermal/shearing pilot plants have produced acceptable slurries for gasification tests from a waste paper feedstock. Work is currently underway with combined paper/plastic feedstocks. When the assembly of the Research Gasification Unit at Texaco (feed capacity approximately 3/4-ton/day) is complete (4th quarter of FY96), gasification test runs will commence. Laboratory work on slurry samples during FY96 has provided correlations between slurry viscosity and hydrothermal treatment temperature, degree of shearing, and the presence of surfactants and admixed plastics. To date, pumpable slurries obtained from an MSW surrogate mixture of treated paper and plastic have shown heating values in the range 13-15 MJ/kg. Our process modeling has quantified the relationship between slurry heating value and hydrogen yield. LLNL has also performed a preliminary cost analysis of the process with the slurry heating value and the MSW tipping fee as parameters. This analysis has shown that the overall process with a 15 MJ/kg slurry gasifier feed can compete with coal-derived hydrogen with the assumption that the tipping fee is of the order $50/ton.

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

Science.gov (United States)

2013-06-21

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

Immobilization in ceramic waste forms of the residues from treatment of mixed wastes

International Nuclear Information System (INIS)

Oversby, V.M.; van Konynenburg, R.A.; Glassley, W.E.; Curtis, P.G.

1993-11-01

The Environmental Restoration and Waste Management Applied Technology Program at LLNL is developing a Mixed Waste Management Facility to demonstrate treatment technologies that provide an alternative to incineration. As part of that program, we are developing final waste forms using ceramic processing methods for the immobilization of the treatment process residues. The ceramic phase assemblages are based on using Synroc D as a starting point and varying the phase assemblage to accommodate the differences in chemistry between the treatment process residues and the defense waste for which Synroc D was developed. Two basic formulations are used, one for low ash residues resulting from treatment of organic materials contaminated with RCRA metals, and one for high ash residues generated from the treatment of plastics and paper products. Treatment process residues are mixed with ceramic precursor materials, dried, calcined, formed into pellets at room temperature, and sintered at 1150 to 1200 degrees C to produce the final waste form. This paper discusses the chemical composition of the waste streams and waste forms, the phase assemblages that serve as hosts for inorganic waste elements, and the changes in waste form characteristics as a function of variation in process parameters

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.

Final report for the 1996 DOE grant supporting research at the SLAC/LBNL/LLNL B factory

International Nuclear Information System (INIS)

Judd, D.; Wright, D.

1997-01-01

This final report discusses Department of Energy-supported research funded through Lawrence Livermore National Laboratory (LLNL) which was performed as part of a collaboration between LLNL and Prairie View A and M University to develop part of the BaBar detector at the SLAC B Factory. This work focuses on the Instrumented Flux Return (IFR) subsystem of BaBar and involves a full range of detector development activities: computer simulations of detector performance, creation of reconstruction algorithms, and detector hardware R and D. Lawrence Livermore National Laboratory has a leading role in the IFR subsystem and has established on-site computing and detector facilities to conduct this research. By establishing ties with the existing LLNL Research Collaboration Program and leveraging LLNL resources, the experienced Prairie View group was able to quickly achieve a more prominent role within the BaBar collaboration and make significant contributions to the detector design. In addition, this work provided the first entry point for Historically Black Colleges and Universities into the B Factory collaboration, and created an opportunity to train a new generation of minority students at the premier electron-positron high energy physics facility in the US

Performance of HEPA filters at LLNL following the 1980 and 1989 earthquakes

International Nuclear Information System (INIS)

Bergman, W.; Elliott, J.; Wilson, K.

1995-01-01

The Lawrence Livermore National Laboratory has experienced two significant earthquakes for which data is available to assess the ability of HEPA filters to withstand seismic conditions. A 5.9 magnitude earthquake with an epicenter 10 miles from LLNL struck on January 24, l980. Estimates of the peak ground accelerations ranged from 0.2 to 0.3 g. A 7.0 magnitude earthquake with an epicenter about 50 miles from LLNL struck on October 17, 1989. Measurements of the ground accelerations at LLNL averaged 0.1 g. The results from the in-place filter tests obtained after each of the earthquakes were compiled and studied to determine if the earthquakes had caused filter leakage. Our study showed that only the 1980 earthquake resulted in a small increase in the number of HEPA filters developing leaks. In the 12 months following the 1980 and 1989 earthquakes, the in-place filter tests showed 8.0% and 4.1% of all filters respectively developed leaks. The average percentage of filters developing leaks from 1980 to 1993 was 3.3%+/-1.7%. The increase in the filter leaks is significant for the 1980 earthquake, but not for the 1989 earthquake. No contamination was detected following the earthquakes that would suggest transient releases from the filtration system

Performance of HEPA filters at LLNL following the 1980 and 1989 earthquakes

Energy Technology Data Exchange (ETDEWEB)

Bergman, W.; Elliott, J.; Wilson, K. [Lawrence Livermore National Laboratory, CA (United States)

1995-02-01

The Lawrence Livermore National Laboratory has experienced two significant earthquakes for which data is available to assess the ability of HEPA filters to withstand seismic conditions. A 5.9 magnitude earthquake with an epicenter 10 miles from LLNL struck on January 24, l980. Estimates of the peak ground accelerations ranged from 0.2 to 0.3 g. A 7.0 magnitude earthquake with an epicenter about 50 miles from LLNL struck on October 17, 1989. Measurements of the ground accelerations at LLNL averaged 0.1 g. The results from the in-place filter tests obtained after each of the earthquakes were compiled and studied to determine if the earthquakes had caused filter leakage. Our study showed that only the 1980 earthquake resulted in a small increase in the number of HEPA filters developing leaks. In the 12 months following the 1980 and 1989 earthquakes, the in-place filter tests showed 8.0% and 4.1% of all filters respectively developed leaks. The average percentage of filters developing leaks from 1980 to 1993 was 3.3%+/-1.7%. The increase in the filter leaks is significant for the 1980 earthquake, but not for the 1989 earthquake. No contamination was detected following the earthquakes that would suggest transient releases from the filtration system.

The design and implementation of the LLNL gigabit testbed

Energy Technology Data Exchange (ETDEWEB)

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

1994-12-01

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

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

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

Energy Technology Data Exchange (ETDEWEB)

Daily III, W D

2010-02-24

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

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)

Comprehensive Angular Response Study of LLNL Panasonic Dosimeter Configurations and Artificial Intelligence Algorithm

Energy Technology Data Exchange (ETDEWEB)

Stone, D. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-06-30

In April of 2016, the Lawrence Livermore National Laboratory External Dosimetry Program underwent a Department of Energy Laboratory Accreditation Program (DOELAP) on-site assessment. The assessment reported a concern that the study performed in 2013 Angular Dependence Study Panasonic UD-802 and UD-810 Dosimeters LLNL Artificial Intelligence Algorithm was incomplete. Only the responses at ±60° and 0° were evaluated and independent data from dosimeters was not used to evaluate the algorithm. Additionally, other configurations of LLNL dosimeters were not considered in this study. This includes nuclear accident dosimeters (NAD) which are placed in the wells surrounding the TLD in the dosimeter holder.

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.

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

Universal requisition for waste data collection

Energy Technology Data Exchange (ETDEWEB)

Nisbet, B.; Gage, M.

1995-05-01

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

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.

Physics of laser fusion. Volume II. Diagnostics of experiments on laser fusion targets at LLNL

Energy Technology Data Exchange (ETDEWEB)

Ahlstrom, H.G.

1982-01-01

These notes present the experimental basis and status for laser fusion as developed at LLNL. There are two other volumes in this series: Vol. I, by C.E. Max, presents the theoretical laser-plasma interaction physics; Vol. III, by J.F. Holzrichter et al., presents the theory and design of high-power pulsed lasers. A fourth volume will present the theoretical implosion physics. The notes consist of six sections. The first, an introductory section, provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLNL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLNL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future.

Physics of laser fusion. Volume II. Diagnostics of experiments on laser fusion targets at LLNL

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1982-01-01

These notes present the experimental basis and status for laser fusion as developed at LLNL. There are two other volumes in this series: Vol. I, by C.E. Max, presents the theoretical laser-plasma interaction physics; Vol. III, by J.F. Holzrichter et al., presents the theory and design of high-power pulsed lasers. A fourth volume will present the theoretical implosion physics. The notes consist of six sections. The first, an introductory section, provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLNL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLNL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

Energy Technology Data Exchange (ETDEWEB)

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

1991-11-12

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A P CT Drum Scanner at LLNL.

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

Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

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

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.

LLNL Center of Excellence Work Items for Q9-Q10 period

Energy Technology Data Exchange (ETDEWEB)

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

2016-09-02

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

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)

Report on the B-Fields at NIF Workshop Held at LLNL October 12-13, 2015

International Nuclear Information System (INIS)

Fournier, K. B.; Moody, J. D.

2015-01-01

A national ICF laboratory workshop on requirements for a magnetized target capability on NIF was held by NIF at LLNL on October 12 and 13, attended by experts from LLNL, SNL, LLE, LANL, GA, and NRL. Advocates for indirect drive (LLNL), magnetic (Z) drive (SNL), polar direct drive (LLE), and basic science needing applied B (many institutions) presented and discussed requirements for the magnetized target capabilities they would like to see. 30T capability was most frequently requested. A phased operation increasing the field in steps experimentally can be envisioned. The NIF management will take the inputs from the scientific community represented at the workshop and recommend pulse-powered magnet parameters for NIF that best meet the collective user requests. In parallel, LLNL will continue investigating magnets for future generations that might be powered by compact laser-B-field generators (Moody, Fujioka, Santos, Woolsey, Pollock). The NIF facility engineers will start to analyze compatibility of the recommended pulsed magnet parameters (size, field, rise time, materials) with NIF chamber constraints, diagnostic access, and final optics protection against debris in FY16. The objective of this assessment will be to develop a schedule for achieving an initial Bfield capability. Based on an initial assessment, room temperature magnetized gas capsules will be fielded on NIF first. Magnetized cryo-ice-layered targets will take longer (more compatibility issues). Magnetized wetted foam DT targets (Olson) may have somewhat fewer compatibility issues making them a more likely choice for the first cryo-ice-layered target fielded with applied Bz.

Hazardous and Medical Waste Destruction Using the AC Plasmatron Final Report CRADA No. TC-1560-98

Energy Technology Data Exchange (ETDEWEB)

Caplan, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bucher, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tulupov, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-09-28

The goal of this project was to develop a prototype medical waste destruction facility based on the AC plasma torch capable of processing 150 kg of waste per hour while satisfying US EPA emission standards. The project was to provide the first opportunity for a joint U.S.-Russian project using an AC Plasma Torch in a hazardous waste destruction system to be assembled and operated in the U.S. thus promoting the commercialization in the U.S. of this joint U.S.-Russian developed technology. This project was a collaboration between the Russian Institute Soliton- NTT, the U.S industrial partner Scientific Utilization Inc. (SUI) and Lawrence Livermore National Laboratory ( LLNL). The project was funded by DOE for a total of $1.2 million with $600K for allocated for Phase I and $600K for Phase II. The Russian team received about $800K over the two (2) year period while LLNL received $400K. SUI was to provide in kind matching funds totaling $1.2 million.

Preliminary selection criteria for the Yucca Mountain Project waste package container material

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

Beam-beam studies for the proposed SLAC/LBL/LLNL B Factory

International Nuclear Information System (INIS)

Furman, M.A.

1991-05-01

We present a summary of beam-beam dynamics studies that have been carried out to date for the proposed SLAC/LBL/LLNL B Factory. Most of the material presented here is contained in the proposal's Conceptual Design Report, although post-CDR studies are also presented. 15 refs., 6 figs., 2 tabs

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

Joint research and development and exchange of technology on toxic material emergency response between LLNL and ENEA. 1985 progress report

International Nuclear Information System (INIS)

Dickerson, M.H.; Caracciolo, R.

1986-01-01

For the past six years, the US Department of Energy, LLNL, and the ENEA, Rome, Italy, have participated in cooperative studies for improving a systems approach to an emergency response following nuclear accidents. Technology exchange between LLNL and the ENEA was initially confined to the development, application, and evaluation of atmospheric transport and diffusion models. With the emergence of compatible hardware configurations between LLNL and ENEA, exchanges of technology and ideas for improving the development and implementation of systems are beginning to emerge. This report describes cooperative work that has occurred during the past three years, the present state of each system, and recommendations for future exchanges of technology

A Novel Approach to Semantic and Coreference Annotation at LLNL

Energy Technology Data Exchange (ETDEWEB)

Firpo, M

2005-02-04

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

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

International Nuclear Information System (INIS)

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

1991-01-01

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A ampersand P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A ampersand P CT Drum Scanner at LLNL

Remote waste handling and feed preparation for Mixed Waste Management

International Nuclear Information System (INIS)

Couture, S.A.; Merrill, R.D.; Densley, P.J.

1995-05-01

The Mixed Waste Management Facility (MWMF) at the Lawrence Livermore National Laboratory (LLNL) will serve as a national testbed to demonstrate mature mixed waste handling and treatment technologies in a complete front-end to back-end --facility (1). Remote operations, modular processing units and telerobotics for initial waste characterization, sorting and feed preparation have been demonstrated at the bench scale and have been selected for demonstration in MWMF. The goal of the Feed Preparation design team was to design and deploy a robust system that meets the initial waste preparation flexibility and productivity needs while providing a smooth upgrade path to incorporate technology advances as they occur. The selection of telerobotics for remote handling in MWMF was made based on a number of factors -- personnel protection, waste generation, maturity, cost, flexibility and extendibility. Modular processing units were selected to enable processing flexibility and facilitate reconfiguration as new treatment processes or waste streams are brought on line for demonstration. Modularity will be achieved through standard interfaces for mechanical attachment as well as process utilities, feeds and effluents. This will facilitate reconfiguration of contaminated systems without drilling, cutting or welding of contaminated materials and with a minimum of operator contact. Modular interfaces also provide a standard connection and disconnection method that can be engineered to allow convenient remote operation

Documented Safety Analysis for the Waste Storage Facilities March 2010

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2010-03-05

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

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.

LLNL (Lawrence Livermore National Laboratory) research on cold fusion

Energy Technology Data Exchange (ETDEWEB)

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

1989-09-14

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

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

International Nuclear Information System (INIS)

1987-09-01

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

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Russell, E.W.; Clarke, W. [Lawrence Livermore National Lab., CA (United States); Domian, H.A. [Babcock and Wilcox Co., Lynchburg, VA (United States); Madson, A.A. [Kaiser Engineers California Corp., Oakland, CA (United States)

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B&S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs.

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Russell, E.W.; Clarke, W.; Domian, H.A.; Madson, A.A.

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B ampersand S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs

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

Seismic evaluation of the LLNL plutonium facility (Building 332)

International Nuclear Information System (INIS)

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

1982-03-01

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

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.

Appendix D-12A Building 332C Waste Accumulation Area

International Nuclear Information System (INIS)

Chase, D

2005-01-01

This appendix is designed to provide information specific to the Building 332C Waste Accumulation Area (B-332C WAA), a waste storage area. This appendix is not designed to be used as a sole source of information. All general information that is not specific to the B-332C WAA is included in the Contingency Plan for Waste Accumulation Areas, dated July 2004, and should be referenced. The B-332C WAA is located in the southwest quadrant of the LLNL Main Site in Building 332, Room 1330. Hazardous and mixed wastes may be stored at the B-332C WAA for 90 days or less, until transferred to the appropriate Radioactive and Hazardous Waste Management (RHWM) facility or other permitted treatment, storage or disposal facility (TSDF). Radioactive waste may also be stored at the WAA. The design storage capacity of this WAA is 2,200 gallons

Institute of Geophysics and Planetary Physics (IGPP), Lawrence Livermore National Laboratory (LLNL): Quinquennial report, November 14-15, 1996

Energy Technology Data Exchange (ETDEWEB)

Tweed, J.

1996-10-01

This Quinquennial Review Report of the Lawrence Livermore National Laboratory (LLNL) branch of the Institute for Geophysics and Planetary Physics (IGPP) provides an overview of IGPP-LLNL, its mission, and research highlights of current scientific activities. This report also presents an overview of the University Collaborative Research Program (UCRP), a summary of the UCRP Fiscal Year 1997 proposal process and the project selection list, a funding summary for 1993-1996, seminars presented, and scientific publications. 2 figs., 3 tabs.

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%.

Mediated electrochemical oxidation as an alternative to incineration for mixed wastes

International Nuclear Information System (INIS)

Chiba, Z.; Schumacher, B.; Lewis, P.; Murguia, L.

1995-02-01

Mediated Electrochemical Oxidation (MEO) is an aqueous process which oxidizes organics electrochemically at low temperatures and ambient pressures. The process can be used to treat mixed wastes containing hazardous organics by destroying the organic components of the wastes. The radioactive components of the wastes are dissolved in the electrolyte where they can be recovered if desired, or immobilized for disposal. The process of destroying organics is accomplished via a mediator, which is in the form of metallic ions in solution. At Lawrence Livermore National Laboratory (LLNL) we have worked with worked with several mediators, including silver, cobalt and cerium. We have tested mediators in nitric as well as sulfuric acids. We have recently completed extensive experimental studies on cobalt-sulfuric acid and silver-nitric acid systems for destroying the major organic components of Rocky Flats Plant combustible mixed wastes. Organics tested were: Trimsol (a cutting oil), cellulose (including paper and cloth), rubber (latex), plastics (Tyvek, polyethylene and polyvinyl chloride) and biomass (bacteria). The process was capable of destroying almost all of the organics tested, attaining high destruction efficiencies at reasonable coulombic efficiencies. The only exception was polyvinyl chloride, which was destroyed very slowly resulting in poor coulombic efficiencies. Besides the process development work mentioned above, we are working on the design of a pilot-plant scale integrated system to be installed in the Mixed Waste Management Facility (MWMF) at LLNL. The system will also be completely integrated with upstream and downstream processes (for example, feed preparation, off-gas and water treatment, and final forms encapsulation). The conceptual design for the NEO-MWMF system has been completed and preliminary design work has been initiated. Demonstration of the process with low-level mixed wastes is expected to commence in 1998

Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)

International Nuclear Information System (INIS)

Riley, D.; Dodson, K.

2007-01-01

This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched

Over Batch Analysis for the LLNL DOE-STD-3013 Packaging System

International Nuclear Information System (INIS)

Riley, D.C.; Dodson, K.

2009-01-01

This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched.

Final report on the LLNL compact torus acceleration project

International Nuclear Information System (INIS)

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

1995-01-01

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

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

FY14 LLNL OMEGA Experimental Programs

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-13

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

FY15 LLNL OMEGA Experimental Programs

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-04

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

Real-time radiography, digital radiography, and computed tomography for nonintrusive waste drum characterization

International Nuclear Information System (INIS)

Martz, H.E.; Schneberk, D.J.; Roberson, G.P.

1994-07-01

We are investigating and developing the application of x-ray nondestructive evaluation (NDE) and gamma-ray nondestructive assay (NDA) methods to nonintrusively characterize 208-liter (55-gallon) mixed waste drums. Mixed wastes contain both hazardous and radioactive materials. We are investigating the use of x-ray NDE methods to verify the content of documented waste drums and determine if they can be used to identify hazardous and nonconforming materials. These NDE methods are also being used to help waste certification and hazardous waste management personnel at LLNL to verify/confirm and/or determine the contents of waste. The gamma-ray NDA method is used to identify the intrinsic radioactive source(s) and to accurately quantify its strength. The NDA method may also be able to identify some hazardous materials such as heavy metals. Also, we are exploring techniques to combine both NDE and NDA data sets to yield the maximum information from these nonintrusive, waste-drum characterization methods. In this paper, we report an our x-ray NDE R ampersand D activities, while our gamma-ray NDA activities are reported elsewhere in the proceedings. We have developed a data, acquisition scanner for x-ray NDE real-time radiography (RTR), as well as digital radiography transmission computed tomography (TCT) along with associated computational techniques for image reconstruction, analysis, and display. We are using this scanner and real-waste drums at Lawrence Livermore National Laboratory (LLNL). In this paper, we discuss some issues associated with x-ray imaging, describe the design construction of an inexpensive NDE drum scanner, provide representative DR and TCT results of both mock- and real-waste drums, and end with a summary of our efforts and future directions. The results of these scans reveal that RTR, DR, and CT imaging techniques can be used in concert to provide valuable information about the interior of low-level-, transuranic-, and mock-waste drums without

Closure development for high-level nuclear waste containers for the tuff repository

International Nuclear Information System (INIS)

Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P.; Babcock and Wilcox Co., Alliance, OH

1990-09-01

This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs

DOE/LLNL verification symposium on technologies for monitoring nuclear tests related to weapons proliferation

International Nuclear Information System (INIS)

Nakanishi, K.K.

1993-01-01

The rapidly changing world situation has raised concerns regarding the proliferation of nuclear weapons and the ability to monitor a possible clandestine nuclear testing program. To address these issues, Lawrence Livermore National Laboratory's (LLNL) Treaty Verification Program sponsored a symposium funded by the US Department of Energy's (DOE) Office of Arms Control, Division of Systems and Technology. The DOE/LLNL Symposium on Technologies for Monitoring Nuclear Tests Related to Weapons Proliferation was held at the DOE's Nevada Operations Office in Las Vegas, May 6--7,1992. This volume is a collection of several papers presented at the symposium. Several experts in monitoring technology presented invited talks assessing the status of monitoring technology with emphasis on the deficient areas requiring more attention in the future. In addition, several speakers discussed proliferation monitoring technologies being developed by the DOE's weapons laboratories

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.

Advanced robotics handling and controls applied to Mixed Waste characterization, segregation and treatment

International Nuclear Information System (INIS)

Grasz, E.; Huber, L.; Horvath, J.; Roberson, P.; Wilhelmsen, K.; Ryon, R.

1994-11-01

At Lawrence Livermore National Laboratory under the Mixed Waste Operations program of the Department of Energy Robotic Technology Development Program (RTDP), a key emphasis is developing a total solution to the problem of characterizing, handling and treating complex and potentially unknown mixed waste objects. LLNL has been successful at looking at the problem from a system perspective and addressing some of the key issues including non-destructive evaluation of the waste stream prior to the materials entering the handling workcell, the level of automated material handling required for effective processing of the waste stream objects (both autonomous and tele-operational), and the required intelligent robotic control to carry out the characterization, segregation, and waste treating processes. These technologies were integrated and demonstrated in a prototypical surface decontamination workcell this past year

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

Protecting worker health and safety using remote handling systems

International Nuclear Information System (INIS)

Dennison, D.K.; Merrill, R.D.; Reed, R.K.

1995-03-01

Lawrence Livermore National Laboratory (LLNL) is currently developing and installing two large-scale, remotely controlled systems for use in improving worker health and safety by minimizing exposure to hazardous and radioactive materials. The first system is a full-scale liquid feed system for use in delivering chemical reagents to LLNL's existing aqueous low-level radioactive and mixed waste treatment facility (Tank Farm). The Tank Farm facility is used to remove radioactive and toxic materials in aqueous wastes prior to discharge to the City of Livermore Water Reclamation Plant (LWRP), in accordance with established discharge limits. Installation of this new reagent feed system improves operational safety and process efficiency by eliminating the need to manually handle reagents used in the treatment processes. This was done by installing a system that can inject precisely metered amounts of various reagents into the treatment tanks and can be controlled either remotely or locally via a programmable logic controller (PLC). The second system uses a robotic manipulator to remotely handle, characterize, process, sort, and repackage hazardous wastes containing tritium. This system uses an IBM-developed gantry robot mounted within a special glove box enclosure designed to isolate tritiated wastes from system operators and minimize the potential for release of tritium to the atmosphere. Tritiated waste handling is performed remotely, using the robot in a teleoperational mode for one-of-a-kind functions and in an autonomous mode for repetitive operations. The system is compatible with an existing portable gas cleanup unit designed to capture any gas-phase tritium inadvertently released into the glove box during waste handling

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

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

Results of LLNL investigation of NYCT data sets

International Nuclear Information System (INIS)

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

2007-01-01

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

Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed

Proposed LLNL electron beam ion trap

International Nuclear Information System (INIS)

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

1985-01-01

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

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

International Nuclear Information System (INIS)

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

1987-01-01

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

Release isentrope measurements with the LLNL electric gun

Energy Technology Data Exchange (ETDEWEB)

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

1987-06-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-25

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

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

International Nuclear Information System (INIS)

Wall, Mark A.

2016-01-01

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

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

Compilation of LLNL CUP-2 Data

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-31

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

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

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

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

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Evaluation of the neutron dose received by personnel at the LLNL

International Nuclear Information System (INIS)

Hankins, D.E.

1982-01-01

This report was prepared to document the techniques being used to evaluate the neutron exposures received by personnel at the LLNL. Two types of evaluations are discussed covering the use of the routine personnel dosimeter and of the albedo neutron dosimeter. Included in the report are field survey results which were used to determine the calibration factors being applied to the dosimeter readings. Calibration procedures are discussed and recommendations are made on calibration and evaluation procedures

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

Description and application of the AERIN Code at LLNL

International Nuclear Information System (INIS)

King, W.C.

1986-01-01

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

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

LLNL Experimental Test Site (Site 300) Potable Water System Operations Plan

Energy Technology Data Exchange (ETDEWEB)

Ocampo, R. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2015-09-14

The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

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.

Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

Larson, H L

2007-09-07

This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and

Status of the SLAC/LBL/LLNL B-factory and the BABAR detector

International Nuclear Information System (INIS)

Oddone, P.

1994-10-01

After a brief introduction on the physics reach of the SLAC/LBL/LLNL Asymmetric B-Factory, the author describes the status of the accelerator and the detector as of the end of 1994. At this time, essentially all major decisions have been made, including the choice of particle identification for the detector. The author concludes this report with the description of the schedule for the construction of both accelerator and detector

The new LLNL AMS sample changer

International Nuclear Information System (INIS)

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

1993-01-01

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

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....

OMICRON, LLNL ENDL Charged Particle Data Library Processing

International Nuclear Information System (INIS)

Mengoni, A.; Panini, G.C.

2002-01-01

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

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

Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report

Energy Technology Data Exchange (ETDEWEB)

Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

1990-09-01

This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

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.

A high-sensitivity neutron counter and waste-drum counting with the high-sensitivity neutron instrument

International Nuclear Information System (INIS)

Hankins, D.E.; Thorngate, J.H.

1993-04-01

At Lawrence Livermore National Laboratory (LLNL), a highly sensitive neutron counter was developed that can detect and accurately measure the neutrons from small quantities of plutonium or from other low-level neutron sources. This neutron counter was originally designed to survey waste containers leaving the Plutonium Facility. However, it has proven to be useful in other research applications requiring a high-sensitivity neutron instrument

Organic waste processing using molten salt oxidation

Energy Technology Data Exchange (ETDEWEB)

Adamson, M. G., LLNL

1998-03-01

Molten Salt Oxidation (MSO) is a thermal means of oxidizing (destroying) the organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. The U. S. Department of Energy`s Office of Environmental Management (DOE/EM) is currently funding research that will identify alternatives to incineration for the treatment of organic-based mixed wastes. (Mixed wastes are defined as waste streams which have both hazardous and radioactive properties.) One such project is Lawrence Livermore National Laboratory`s Expedited Technology Demonstration of Molten Salt Oxidation (MSO). The goal of this project is to conduct an integrated demonstration of MSO, including off-gas and spent salt treatment, and the preparation of robust solid final forms. Livermore National Laboratory (LLNL) has constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are presently being performed under carefully controlled (experimental) conditions. The system consists of a MSO process vessel with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. In this paper we describe the integrated system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is to identify the most suitable waste streams and waste types for MSO treatment.

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

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.

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

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

International Nuclear Information System (INIS)

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

2007-01-01

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

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

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.