Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

International Nuclear Information System (INIS)

McLaughlin, T.J.

1998-01-01

This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

Technical area status report for low-level mixed waste final waste forms

International Nuclear Information System (INIS)

Mayberry, J.L.; DeWitt, L.M.; Darnell, R.

1993-08-01

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA's Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

Long-term high-level waste technology. Composite quarterly technical report, July-September 1980

International Nuclear Information System (INIS)

Cornman, W.R.

1981-02-01

This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The technical information included in this report is structured along the lines of the Work Breakdown Structure adopted for use in the High-Level Waste Management Technology (WBS) program. The functions and work elements of the WBS are as follows: function 1 - program management and support, which includes work elements of management and budget, environmental and safety assessments, and other support; function 2 - waste preparation, which includes in-situ storage or disposal, waste retrieval, and separation and concentration; function 3 - waste fixation with work elements of waste form development and characterization, and process and equipment development; and function 4 - final handling which includes canister development and characterization, and onsite storage or disposal

Engineering Technical Support Center Annual Report Fiscal ...

Science.gov (United States)

The United States Environmental Protection Agency (EPA or Agency) Office of Research and Development (ORD) created the Engineering Technical Support Center (ETSC) in 1987, one of several technical support centers created as part of the Technical Support Project (TSP). ETSC provides engineering expertise to Agency program and regional offices and remediation teams working at contaminated sites across the country. The ETSC is operated within ORD’s Land Remediation and Pollution Control Division (LRPCD) of the National Risk Management Research Laboratory (NRMRL) in Cincinnati, Ohio. The ETSC’s mission is to provide site-specific scientific and engineering technical support to Remedial Project Managers, On-Scene Coordinators, and other remediation personnel at contaminated sites. This allows local, regional, or national authorities to work more quickly, efficiently, and cost effectively, while also increasing the technical experience of the remediation team. Since its inception, the ETSC has supported countless projects across all EPA Regions in almost all states and territories. This report highlights significant projects the ETSC supported in fiscal year 2015 (FY15). These projects addressed an array of environmental scenarios, such as remote mining contamination, expansive landfill waste, cumulative impacts from multiple contamination sources, and persistent threats from abandoned industrial sites. Constructing and testing new and innovative treatment technol

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1992--September 1993

International Nuclear Information System (INIS)

Bates, J.K.; Bourcier, W.L.; Bradley, C.R.

1994-06-01

This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal

Technical area status report for low-level mixed waste final waste forms. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Mayberry, J.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-08-01

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA`s Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities.

Transuranic waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

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

1980-12-01

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

Regulatory Support of Treatment of Savannah River Site Purex Waste

International Nuclear Information System (INIS)

Reid, L.T.

2009-01-01

This paper describes the support given by federal and state regulatory agencies to Savannah River Site (SRS) during the treatment of an organic liquid mixed waste from the Plutonium Extraction (Purex) process. The support from these agencies allowed (SRS) to overcome several technical and regulatory barriers and treat the Purex waste such that it met LDR treatment standards. (authors)

RE/SPEC Inc. technical support to the Repository Technology Program

International Nuclear Information System (INIS)

Wagner, R.A.

1992-06-01

This report presents a summary of all RE/SPEC Inc. technical support activities to the Repository Technology Program (RTP) from September 1, 1988, through June 30, 1992. The RE/SPEC Inc. activities are grouped into the following categories: project management, project quality assurance (QA), performance assessment (PA), support of the Office of Civilian Radioactive Waste Management (OCRWM) through technical reviews and general assistance, participation in the Department of Energy (DOE) International Program, and code evaluation and documentation

Technical responsibilities in low-level waste disposal

International Nuclear Information System (INIS)

Murray, R.L.; Walker, C.K.

1989-01-01

North Carolina will be the host state for a low-level radioactive waste (LLRW) disposal facility serving the Southeast Compact for 20 yr beginning in 1993. Primary responsibility for the project rests with the North Carolina Low-Level Radioactive Waste Management Authority, a citizen board. The North Carolina project embodies a unique combination of factors that places the authority in a position to exercise technical leadership in the LLRW disposal field. First, the Southeast Compact is the largest in the United States in terms of area, population, and waste generation. second, it is in a humid rather than an arid region. Third, the citizens of the state are intensely interested in preserving life style, environment, and attractiveness of the region to tourists and are especially sensitive to the presence of waste facilities of any kind. Finally, disposal rules set by the Radiation Protection Commission and enforced by the Radiation Protection Section are stricter than the U.S. Nuclear Regulatory Commission's 10CFR61. These four factors support the authority's belief that development of the facility cannot be based solely on engineering and economics, but that social factors, including perceptions of human risk, concerns for the environment, and opinions about the desirability of hosting a facility, should be integral to the project. This philosophy guides the project's many technical aspects, including site selection, site characterization, technology selection and facility design, performance assessment modeling, and waste reduction policies. Each aspect presents its own unique problems

Technical Support Essentials Advice to Succeed in Technical Support

CERN Document Server

Sanchez, Andrew

2010-01-01

Technical Support Essentials is a book about the many facets of technical support. It attempts to provide a wide array of topics to serve as points of improvement, discussion, or simply topics that you might want to learn. The topics range from good work habits to the way technical supportgroups establish their own style of work. This book applies theories, models, and concepts synthesized from existing research in other fields-such as management, economics, leadership, and psychology-and connects them to technical support. The goal is to build on the work of others and allow their success to

National Waste Terminal Storage Program: management and technical program plan, FY 1976--FY 1978

International Nuclear Information System (INIS)

1976-01-01

The discussion on the management plan covers the program, responsibilities, general program schedule and logic, Office of Waste Isolation organization and facilities, management approach, administrative plan, and public affairs plan. The technical program plan includes geological studies, technical support studies, engineering studies, waste facility projects, environmental studies, system studies, data management, and international activities. The information contained in this report is obsolete and of historical interest only

Support for designing waste sorting systems: A mini review.

Science.gov (United States)

Rousta, Kamran; Ordoñez, Isabel; Bolton, Kim; Dahlén, Lisa

2017-11-01

This article presents a mini review of research aimed at understanding material recovery from municipal solid waste. It focuses on two areas, waste sorting behaviour and collection systems, so that research on the link between these areas could be identified and evaluated. The main results presented and the methods used in the articles are categorised and appraised. The mini review reveals that most of the work that offered design guidelines for waste management systems was based on optimising technical aspects only. In contrast, most of the work that focused on user involvement did not consider developing the technical aspects of the system, but was limited to studies of user behaviour. The only clear consensus among the articles that link user involvement with the technical system is that convenient waste collection infrastructure is crucial for supporting source separation. This mini review reveals that even though the connection between sorting behaviour and technical infrastructure has been explored and described in some articles, there is still a gap when using this knowledge to design waste sorting systems. Future research in this field would benefit from being multidisciplinary and from using complementary methods, so that holistic solutions for material recirculation can be identified. It would be beneficial to actively involve users when developing sorting infrastructures, to be sure to provide a waste management system that will be properly used by them.

Technical area status report for waste destruction and stabilization

International Nuclear Information System (INIS)

Dalton, J.D.; Harris, T.L.; DeWitt, L.M.

1993-08-01

The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs/activities throughout the DOE complex. In order to successfully achieve the goal of properly managing waste and the cleanup of the DOE sites, the EM was divided into five organizations: the Office of Planning and Resource Management (EM-10); the Office of Environmental Quality Assurance and Resource Management (EM-20); the Office of Waste Operations (EM-30); the Office of Environmental Restoration (EM-40); and the Office of Technology and Development (EM-50). The mission of the Office of Technology Development (OTD) is to develop treatment technologies for DOE's operational and environmental restoration wastes where current treatment technologies are inadequate or not available. The Mixed Waste Integrated Program (MWIP) was created by OTD to assist in the development of treatment technologies for the DOE mixed low-level wastes (MLLW). The MWIP has established five Technical Support Groups (TSGs) whose purpose is to identify, evaluate, and develop treatment technologies within five general technical areas representing waste treatment functions from initial waste handling through generation of final waste forms. These TSGs are: (1) Front-End Waste Handling, (2) Physical/Chemical Treatment, (3) Waste Destruction and Stabilization, (4) Second-Stage Destruction and Offgas Treatment, and (5) Final Waste Forms. This report describes the functions of the Waste Destruction and Stabilization (WDS) group. Specifically, the following items are discussed: DOE waste stream identification; summary of previous efforts; summary of WDS treatment technologies; currently funded WDS activities; and recommendations for future activities

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-01-01

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

ANL technical support program for DOE Environmental Restoration and Waste Management

International Nuclear Information System (INIS)

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J.; Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L.; Ewing, R.C.; Wang, L.; Li, H.; Tomozawa, M.

1993-05-01

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program

International Nuclear Information System (INIS)

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01

This document provides guidance for the revision of DOE Order 5820.2A, ''Radioactive Waste Management.'' Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

International Nuclear Information System (INIS)

KOZLOWSKI, S.D.

2007-01-01

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

Low-level waste program technical strategy

International Nuclear Information System (INIS)

Bledsoe, K.W.

1994-01-01

The Low-Level Waste Technical Strategy document describes the mechanisms which the Low-Level Waste Program Office plans to implement to achieve its mission. The mission is to manage the receipt, immobilization, packaging, storage/disposal and RCRA closure (of the site) of the low-level Hanford waste (pretreated tank wastes) in an environmentally sound, safe and cost-effective manner. The primary objective of the TWRS Low-level waste Program office is to vitrify the LLW fraction of the tank waste and dispose of it onsite

Technical and economic evaluation of controlled disposal options for very low level radioactive wastes

International Nuclear Information System (INIS)

Robinson, P.J.; Vance, J.N.

1990-08-01

Over the past several years, there has been considerable interest by the nuclear industry in the Nuclear Regulatory Commission (NRC) explicitly defined an activity level in plant waste materials at which the radiological impacts would be so low as to be considered Below Regulatory Concern (BRC). In January 1989, Electric Power Research Institute (EPRI) completed an extensive industry research effort to develop the technical bases for establishing criteria for the disposal of very low activity wastes in ordinary disposal facilities. The Nuclear Management and Resources Council (NUMARC), with assistance from the Edison Electric Institute (EEI) and the Electric Power Research Institute (EPRI), drafted a petition titled: ''Petition for Rulemaking Regarding Disposal of Below Regulatory Concern Radioactive Wastes from Commercial Nuclear Power Plants.'' Subsequent to the industry making a final decision for submittal of the drafted BRC petition, EPRI was requested to evaluate the technical and economic impact of six BRC options. These options are: take no action in pursuing a BRC waste exemption, petition the NRC for authorization to disposal of any BRC waste in any ordinary disposal facility, limit disposal of BRC waste to the nuclear power plant site, limit disposal of BRC waste to the nuclear power plant site and other utility owned property, petition for a mixed waste exemption, and petition for single waste stream exemptions in sequence (i.e. soil, followed by sewage sludge, etc.). The petition and technical bases were written to support the disposal of any BRC waste type in any ordinary disposal facility. These documents do not provide all of the technical and economic information needed to completely assessment the BRC options. This report provides the technical and economic basis for a range of options concerning disposal of very low activity wastes. 3 figs., 20 tabs

US Department of Energy mixed waste characterization, treatment, and disposal focus area technical baseline development process

International Nuclear Information System (INIS)

Roach, J.A.; Gombert, D.

1996-01-01

The US Department of Energy (DOE) created the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet its commitments for treatment of mixed wastes under the Federal Facility Compliance Act (FFCA), and in accordance with the Land Disposal Restrictions (LDR) of the Resource Conservation and Recovery Act (RCRA). Mixed wastes include both mixed low-level waste (MLLW) and mixed transuranic (MTRU) waste. The goal of the MWFA is to develop mixed waste treatment systems to the point of implementation by the Environmental Management (EM) customer. To accomplish this goal, the MWFA is utilizing a three step process. First, the treatment system technology deficiencies were identified and categorized. Second, these identified needs were prioritized. This resulted in a list of technical deficiencies that will be used to develop a technical baseline. The third step, the Technical Baseline Development Process, is currently ongoing. When finalized, the technical baseline will integrate the requirements associated with the identified needs into the planned and ongoing environmental research and technology development activities supported by the MWFA. Completion of this three-step process will result in a comprehensive technology development program that addresses customer identified and prioritized needs. The MWFA technical baseline will be a cost-effective, technically-defensible tool for addressing and resolving DOE's mixed waste problems

Life cycle assessment of waste management systems: Assessing technical externalities

DEFF Research Database (Denmark)

Brogaard, Line Kai-Sørensen

The life cycle assessment (LCA) of a waste management system relies on many internal characteristics such as pollution control systems and recovery efficiencies. It also relies on technical externalities supporting the waste management system in terms of capital goods and energy and material...... for the primary and secondary production of materials, 366 datasets were gathered. The materials in focus were: paper, newsprint, cardboard, corrugated board, glass, aluminium, steel and plastics (HDPE, LDPE, LLDPE, PET, PS, PVC). Only one quarter of these data concerned secondary production, thus underlining...

Nuclear waste glass melter: an update of technical progress

International Nuclear Information System (INIS)

Brouns, R.A.; Hanson, M.S.

1984-08-01

The direct slurry-fed ceramic-lined melter is currently the reference US process for treating defense and civilian high-level liquid waste. Extensive nonradioactive pilot-scale testing at Pacific Northwest Laboratory (PNL) and Savannah River Laboratory has proven the process, defined operating parameters, and identified successful equipment design concepts. Programs at PNL continue to support several of the planned US vitrification plants through preparation of equipment designs and flowsheet testing. Current emphasis is on remotization of equipment, radioactive verification testing, and resolution of remaining technical issues. Development of this technology, technical status, and planned development activities are discussed. 9 references, 4 figures

Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1

International Nuclear Information System (INIS)

1996-01-01

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE's mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies

Geotechnical support and topical studies for nuclear waste geologic repositories

International Nuclear Information System (INIS)

1989-01-01

The present report lists the technical reviews and comments made during the fiscal year 1988 and summarizes the technical progress of the topical studies. In the area of technical assistance, there were numerous activities detailed in the next section. These included 24 geotechnical support activities, including reviews of 6 Study Plans (SP) and participation in 6 SP Review Workshops, review of one whole document Site Characterization Plan (SCP) and participation in the Assembled Document SCP Review Workshops by 6 LBL reviewers; the hosting of a DOE program review, the rewriting of the project statement of work, 2 trips to technical and planning meetings; preparation of proposed work statements for two new topics for DOE, and 5 instances of technical assistance to DOE. These activities are described in a Table in the following section entitled ''Geoscience Technical Support for Nuclear Waste Geologic Repositories.''

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A., Westinghouse Hanford

1996-07-17

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A.

1996-09-20

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Technical Assessment Of Selection Of A Waste Disposal Site

International Nuclear Information System (INIS)

Lee, Bong Hun

1992-04-01

This book gives overall descriptions of technical assessment of selection of a waste disposal site, which deals with standard of selection on incinerator of city waste, the method over assessment of selection of incinerator in city waste, prerequisite of technical assessment for selection of incinerator, waste incinerator and related equipment such as form, structure, quality of material, ventilation device, plumbing system and electrical installation, and total plan like plan of construction and a measure taken against environmental pollution.

TWRS privatization support project waste characterization database development. Volume 1

International Nuclear Information System (INIS)

Brevick, C.H.

1995-11-01

Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford under-ground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105; 241-AW-101, -103, and -105, 241-AZ-101 and-102; and 241-C-109. Sample data were assembled for sixteen radio nuclides and thirty five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created., the master data set, a subset, and an unreviewed data set

Characteristics of mineral nutrition of plants in the bio-technical life support system with human wastes included in mass exchange

Science.gov (United States)

Tikhomirova, Natalia; Ushakova, Sofya; Kalacheva, Galina; Tikhomirov, Alexander

2016-09-01

The study addresses the effectiveness of using ion exchange substrates (IES) to optimize mineral nutrition of plants grown in the nutrient solutions containing oxidized human wastes for application in bio-technical life support systems. The study shows that the addition of IES to the root-inhabited substrate is favorable for the growth of wheat vegetative organs but causes a decrease in the grain yield. By contrast, the addition of IES to the nutrient solution does not influence the growth of vegetative organs but favors normal development of wheat reproductive organs. Thus, to choose the proper method of adjusting the solution with IES, one should take into account specific parameters of plant growth and development and the possibility of multiple recycling of IES based on the liquid products of mineralization of human wastes.

Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition

International Nuclear Information System (INIS)

Leach, C.E.; Galbraith, J.D.; Grant, P.R.; Francuz, D.J.; Schroeder, P.J.

1995-11-01

This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs

Composite quarterly technical report: long-term high-level waste technology, October-December 1980

International Nuclear Information System (INIS)

Cornman, W.R.

1981-04-01

The technical information in this report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The areas reported are in: program management and support; waste preparation; waste fixation; and final handling. Majority of the studies were in the area of waste fixation, some of which are: leaching tests of ceramic forms, high silica glass, graphite powder and other carbon preparations; viscosity measurements for a range of waste-glass compositions from references borosilicate glass to high-alumina glasses; neutron activation analysis for measuring leach rates; preparation of SYNROC D spheres; formulations for preparing ceramics from defense waste composition; development of a pilot-scale glass melter, and kinetic studies of slag formation in glass melters

Identification of technical problems encountered in the shallow land burial of low-level radioactive wastes

International Nuclear Information System (INIS)

Jacobs, D.G.; Epler, J.S.; Rose, R.R.

1980-03-01

A review of problems encountered in the shallow land burial of low-level radioactive wastes has been made in support of the technical aspects of the National Low-Level Waste (LLW) Management Research and Development Program being administered by the Low-Level Waste Management Program Office, Oak Ridge National Laboratory. The operating histories of burial sites at six major DOE and five commercial facilities in the US have been examined and several major problems identified. The problems experienced st the sites have been grouped into general categories dealing with site development, waste characterization, operation, and performance evaluation. Based on this grouping of the problem, a number of major technical issues have been identified which should be incorporated into program plans for further research and development. For each technical issue a discussion is presented relating the issue to a particular problem, identifying some recent or current related research, and suggesting further work necessary for resolving the issue. Major technical issues which have been identified include the need for improved water management, further understanding of the effect of chemical and physical parameters on radionuclide migration, more comprehensive waste records, improved programs for performance monitoring and evaluation, development of better predictive capabilities, evaluation of space utilization, and improved management control

Identification of technical problems encountered in the shallow land burial of low-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Jacobs, D.G.; Epler, J.S.; Rose, R.R.

1980-03-01

A review of problems encountered in the shallow land burial of low-level radioactive wastes has been made in support of the technical aspects of the National Low-Level Waste (LLW) Management Research and Development Program being administered by the Low-Level Waste Management Program Office, Oak Ridge National Laboratory. The operating histories of burial sites at six major DOE and five commercial facilities in the US have been examined and several major problems identified. The problems experienced st the sites have been grouped into general categories dealing with site development, waste characterization, operation, and performance evaluation. Based on this grouping of the problem, a number of major technical issues have been identified which should be incorporated into program plans for further research and development. For each technical issue a discussion is presented relating the issue to a particular problem, identifying some recent or current related research, and suggesting further work necessary for resolving the issue. Major technical issues which have been identified include the need for improved water management, further understanding of the effect of chemical and physical parameters on radionuclide migration, more comprehensive waste records, improved programs for performance monitoring and evaluation, development of better predictive capabilities, evaluation of space utilization, and improved management control.

Disposal of mixed waste: Technical, institutional, and policy factors

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Letourneau, M.J.; Case, J.T.

1996-01-01

In conjunction with the affected States as part of their interactions required by the Federal Facilities Compliance Act, the Department of Energy has been developing a process for a disposal configuration for its mixed low-level waste (MLLW). This effort, spanning more than two years, has reduced the potential disposal sites from 49 to 15. The remaining 15 sites have been subjected to a performance evaluation to determine their strengths and weaknesses for disposal of MLLW. The process has included institutional and policy factors as well as strictly technical analyses, and technical analyses must be supported by technical analyses, and technical analyses must be performed within a framework which includes some institutional considerations, with the institutional considerations selected for inclusion largely a matter of policy. While the disposal configuration process is yet to be completed, the experience to date offers a viable approach for solving some of these issues. Additionally, several factors remain to be addressed before an MLLW disposal configuration can be developed

Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

1993-04-01

This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

TWRS privatization support project waste characterization database development

International Nuclear Information System (INIS)

1995-11-01

Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford underground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105, 241-AW-101, -103, and -105, 241 AZ-101 and -102; and 241-C-109. Sample data were assembled for sixteen radionuclides and thirty-five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created: the master data set, a subset, and an unreviewed data set. The master data set contains waste composition information for Tanks 241-AN-102 and -107, 241-AP-102 and -105, 241-AW-101; and 241-AZ-101 and -102. The subset contains only the validated analytical sample data from the master data set. The unreviewed data set contains all collected but unreviewed sample data for Tanks 241-AN-104, -105, and -106; 241-AP-104; 241-AW-103 and-105; and 241-C-109. The methodology used to review the waste characterization information was found to be an accurate, useful way to separate the invalid or questionable data from the more reliable data. In the future, this methodology should be considered when validating waste characterization information

Recent IAEA activities to support utilisation of cementitious materials in radioactive waste management

International Nuclear Information System (INIS)

Ojowan, M.I.; Samanta, S.K.

2015-01-01

The International Atomic Energy Agency promotes a safe and effective management of radioactive waste and has suitable programmes in place to serve the needs of Member States in this area. In support of these programmes the Waste Technology Section fosters technology transfer, promotes information exchange and cooperative research, as well as builds capacity in Member States to manage radioactive wastes, resulting both from the nuclear fuel cycle and nuclear applications. Technical assistance in pre disposal area covers all of these activities and is delivered through established Agency mechanisms including publication of technical documents. While the Agency does not conduct any in-house research activities, its Coordinated Research Projects (CRPs) foster research in Member States. There are 2 CRPs concerning cementitious materials: a CRP on cements and an on-going CRP on irradiated graphite waste. The CRP on cements has resulted in the recent IAEA publication TECDOC-1701. An important activity concerned with characterisation of cementitious waste forms is the LABONET network of laboratory-based centres of expertise involved in the characterization of low and intermediate level radioactive wastes. The Waste Technology Section is preparing a series of comprehensive state of the art technical handbooks

Transuranic-waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

McKinley, K.B.

1982-11-01

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

Inclusion of products of physicochemical oxidation of organic wastes in matter recycling of biological-technical life support systems.

Science.gov (United States)

Tikhomirov, Alexander A.; Kudenko, Yurii; Trifonov, Sergei; Ushakova, Sofya

Inclusion of products of human and plant wastes' `wet' incineration in 22 medium using alter-nating current into matter recycling of biological-technical life support system (BTLSS) has been considered. Fluid and gaseous components have been shown to be the products of such processing. In particular, the final product contained all necessary for plant cultivation nitrogen forms: NO2, NO3, NH4+. As the base solution included urine than NH4+ form dominated. At human solid wastes' mineralization NO2 NH4+ were registered in approximately equal amount. Comparative analysis of mineral composition of oxidized human wastes' and standard Knop solutions has been carried out. On the grounds of that analysis the dilution methods of solutions prepared with addition of oxidized human wastes for their further use for plant irrigation have been suggested. Reasonable levels of wheat productivity cultivated at use of given solutions have been obtained. CO2, N2 and O2 have been determined to be the main gas components of the gas admixture emitted within the given process. These gases easily integrate in matter recycling process of closed ecosystem. The data of plants' cultivation feasibility in the atmosphere obtained after closing of gas loop including physicochemical facility and vegetation chamber with plants-representatives of LSS phototrophic unit has been received. Conclusion of advance research on creation of matter recycling process in the integrated physical-chemical-biological model system has been drawn.

11. annual report of the technical advisory committee on the nuclear fuel waste management program

International Nuclear Information System (INIS)

1990-10-01

The Eleventh Annual Report of the Technical Advisory Committee (TAC) assesses the scientific and technical progress made within the Canadian Nuclear Fuel Waste Management Program (NFWMP) during the period July 1989 to June 1990. The Committee notes that the general concept of a multibarrier system involving geologic media and engineered systems is based on known technologies and current scientific knowledge, and has gained strong international scientific and engineering support as currently the most feasible and practical. TAC continues to endorse the full investigation of the concept of nuclear waste disposal deep in plutonic formations, such as those in the Canadian Shield

Low-level waste management program: technical program overview

International Nuclear Information System (INIS)

Lowrie, R.S.

1981-01-01

The mission of the technical program is to develop the technology component of the Department of Energy's Low-Level Waste Management Program and to manage research and development, demonstration, and documentation of the technical aspects of the program. Some of the major technology objectives are: develop and demonstrate techniques for waste generation reduction; develop and demonstrate waste treatment, handling and packaging techniques; develop and demonstrate the technology for greater confinement; and develop the technology for remedial action at existing sites. In addition there is the technology transfer objective which is to compile and issue a handbook documenting the technology for each of the above technology objectives

Municipal Solid Waste management

OpenAIRE

Mirakovski, Dejan; Hadzi-Nikolova, Marija; Doneva, Nikolinka

2010-01-01

Waste management covers newly generated waste or waste from an onging process. When steps to reduce or even eliminate waste are to be considered, it is imperative that considerations should include total oversight, technical and management services of the total process.From raw material to the final product this includes technical project management expertise, technical project review and pollution prevention technical support and advocacy.Waste management also includes handling of waste, in...

Preliminary technical data summary defense waste processing facility stage 2

International Nuclear Information System (INIS)

1980-12-01

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

Tank waste remediation system technical baseline summary description

International Nuclear Information System (INIS)

Raymond, R.E.

1998-01-01

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

Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

International Nuclear Information System (INIS)

1992-07-01

The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

Long-term high-level waste technology. Composite quarterly technical report, January-March 1981

International Nuclear Information System (INIS)

Cornman, W.R.

1981-08-01

This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The report is structured along the lines of the Work Breakdown Structure adopted for use in the High-Level Waste Management Technology program. These are: (1) program management and support with subtasks of management and budget, environmental and safety assessments, and other support; (2) waste preparation with subtasks of in-situ storage or disposal, waste retrieval, and separation and concentration; (3) waste fixation with subtasks of waste form development and characterization, and process and equipment development; and (4) final handling with subtasks of canister development and characterization and onsite storage or disposal. Some of the highlights are: preliminary event trees defining possible accidents were completed in the safety assessment of continued in-tank storage of high-level waste at Hanford; two low-cost waste forms (tailored concrete and bitumen) were investigated as candidate immobilization forms at the Hanford in-situ disposal studies of high-level waste; in comparative impact tests at the same impact energy per specimen volume, the same mass of respirable sizes was observed at ANL for SRL Frit 131 glass, SYNROC B ceramic, and SYNROC D ceramic; leaching tests were conducted on alkoxide glasses; glass-ceramic, concrete, and SYNROC D; a process design description was written for the tailored ceramic process

Solid Waste Program technical baseline description

Energy Technology Data Exchange (ETDEWEB)

Carlson, A.B.

1994-07-01

The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

Technical resource documents and technical handbooks for hazardous-wastes management

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Bliss, T.M.

1986-07-01

The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

HANFORD SITE SOLID WASTE MANAGEMENT ENVIRONMENTAL IMPACT STATEMENT TECHNICAL INFORMATION DOCUMENT [SEC 1 THRU 4

International Nuclear Information System (INIS)

FRITZ, L.L.

2004-01-01

This Technical Information Document (TID) provides engineering data to support DOE/EIS-0286, ''Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement''. Assumptions and waste volumes used to calculate engineering data are also provided in this document. This chapter provides a brief description of: the Solid Waste Management Program (including a description of waste types and known characteristics of waste covered under the program), the Hanford Site (including a general discussion of the operating areas), and the alternatives analyzed. The Hanford Site Solid Waste Management Program and DOE/EIS-0286 address solid radioactive waste types generated by various activities from both onsite and offsite generators. The Environmental Restoration (ER) waste management activities are not within the scope of DOE/EIS-0286 or this TID. Activities for processing and disposal of immobilized low-activity waste (ILAW) are not within the scope of the Solid Waste Management Program and this TID

Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-12-01

This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

International Nuclear Information System (INIS)

Little, C.A.

1995-01-01

The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author's responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A

System for technical innovation support

International Nuclear Information System (INIS)

2011-08-01

This book lists field of support system, which includes tax, development work, basic research project, industrial technology, information and communications field, energy field, part and materials field, local industry, the small and medium business such as technical development field, and industry-university collaboration like summary of investment and financing support and guarantee, support of manpower such as brain pool and contact Korea, support of technique like development technology and strategy for patent, support on certification such as company and technical goods, purchase support.

Technical support and emergency centre

International Nuclear Information System (INIS)

Bohun, L.; Kapisovsk y, M.

1997-01-01

This paper presents technical support and emergency management center which will be on two places: Mochovce NPP Emergency Centre (Technical support center and Support working center) and Reserve Emergency Centre in Levice (Reserve emergency center and Environmental Evaluation Center). The main aims of the emergency management centers are: the management and coordination of all persons and organisations; provision of the all information needed to evaluation of the accident and its mitigation; continuous evaluation of the potential or real radiological consequences; taking measure for an early notification of the governmental bodies and the organizations, warning and protection of the public; and other aims. In the next part the data for technical support and emergency centre are discussed

Waste management project technical baseline description

International Nuclear Information System (INIS)

Sederburg, J.P.

1997-01-01

A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project

Basalt Waste Isolation Project Technical Program Evaluation Process: a criteria-based method

International Nuclear Information System (INIS)

Babad, H.; Evans, G.C.; Wolfe, B.A.

1982-01-01

The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the SWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (MWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP wll be further formalized and further applied to the review of BWIP technical activities

Waste-to-energy: Technical, economic and ecological point of views

International Nuclear Information System (INIS)

Cassitto, L.

1997-01-01

Overwhelming waste-recycling should be considered more as a psychological than as a technological method to deal with wastes. The best waste disposal systems should actually grant mass or energy recovery from technical, economic and ecological point-of-views. Highest results seem to be granted by waste-to-energy technologies since energy content is the best preserved property after using materials

Technical conservatism in the design and analysis of a nuclear-waste repository in basalt

International Nuclear Information System (INIS)

Jones, K.A.

1982-01-01

The US Department of Energy's National Waste Terminal Storage Program has adopted a policy of technical conservatism to guide the design and analysis of geologic disposal systems for commercial high-level radioactive waste. Technical conservatism serves as the programmatic philosophy for managing uncertainty in the performance of the disposal system. The implementation of technical conservatism as applied to a nuclear waste repository in basalt is discussed. Preliminary assessments of the performance of the waste package, repository, and site subsystems are compared to key proposed regulatory criteria. The comparison shows that there are substantial safety margins in the predicted performance of the nuclear waste repository in basalt

The 1996 meeting of the national technical workgroup on mixed waste thermal treatment

International Nuclear Information System (INIS)

1996-01-01

The National Technical Workgroup on Mixed Waste Thermal Treatment held its annual meeting in Atlanta Georgia on March 12-14, 1996. The National Technical Workgroup (NTW) and this meeting were sponsored under an interagency agreement between EPA and DOE. The 1996 Annual Meeting was hosted by US DOE Oak Ridge Operations in conjunction with Lockheed Martin Energy Systems - Center for Waste Management. A new feature of the annual meeting was the Permit Writer Panel Session which provided an opportunity for the state and federal permit writers to discuss issues and potential solutions to permitting mixed waste treatment systems. In addition, there was substantial discussion on the impacts of the Waste Combustion Performance Standards on mixed waste thermal treatment which are expected to proposed very soon. The 1996 meeting also focussed on two draft technical resource documents produced by NTW on Waste Analysis Plans and Compliance Test Procedures. Issues discussed included public involvement, waste characterization, and emission issues

Influence of non-technical policies on choices of waste solidification technologies

International Nuclear Information System (INIS)

Trubatch, S.L.

1987-01-01

This paper describes and discusses non-technical policy considerations which may improperly influence decisions on the solidification of low-level radioactive wastes (''LLW''). These policy considerations are contained principally in several State and Federal statutes which regulate various aspects of LLW disposal. One policy consideration in particular, the unqualified bias in favor of volume reduction, is shown to present a substantial potential for leading to technically suboptimal decisions on the appropriate processes for solidifying LLW. To avoid the unintended skewing of technical decisions by non-technical policy considerations, certain current policies may need to be revised to ensure that the choices of waste treatment, including decisions on solidification, are based primarily on reasonable assurance of adequate protection of public health and safety. This goal may be realized in part by basing any disposal fee structure on more than just LLW volume to include consideration of the waste's activity and its difficulty of confinement

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

International Nuclear Information System (INIS)

1980-09-01

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

Feasible way of Human Solid and Liquid Wastes' Inclusion Into Intersystem Mass Exchange of Biological-Technical Life Support Systems

Science.gov (United States)

Ushakova, Sofya; Tikhomirov, Alexander A.; Tikhomirova, Natalia; Kudenko, Yurii; Griboskaya, Illiada; Gros, Jean-Bernard; Lasseur, Christophe

The basic objective arising at use of mineralized human solid and liquid wastes serving as the source of mineral elements for plants cultivation in biological-technical life support systems appears to be NaCl presence in them. The given work is aimed at feasibility study of mineralized human metabolites' utilization for nutrient solutions' preparation for their further employment at a long-term cultivation of uneven-aged wheat and Salicornia europaea L. cenosis in a conveyer regime. Human solid and liquid wastes were mineralized by the "wet incineration" method developed by Yu. Kudenko. On their base the solutions were prepared which were used for cultivation of 5-aged wheat conveyer with the time step-interval of 14 days. Wheat was cultivated by hydroponics method on expanded clay aggregate. For partial demineralization of nutrient solution every two weeks after regular wheat harvesting 12 L of solution was withdrawn from the wheat irrigation tank and used for Salicornia europaea cultivation by the water culture method in a conveyer regime. The Salicornia europaea conveyer was represented by 2 ages with the time step-interval of 14 days. Resulting from repeating withdrawal of the solution used for wheat cultivation, sodium concentration in the wheat irrigation solution did not exceed 400 mg/l, and mineral elements contained in the taken solution were used for Salicornia europaea cultivation. The experiment lasted 7 months. Total wheat biomass productivity averaged 30.1 g*m-2*day-1 at harvest index equal to 36.8The work was carried out under support of SB RAS grant 132 and INTAS 05-1000008-8010

Technical support non-SLB(GCDF)

International Nuclear Information System (INIS)

DePoorter, G.L.; Burton, B.W.

1982-01-01

The Los Alamos National Laboratory is providing technical support for the Greater Confinement Demonstration Facility (GCDF) at the Nevada Test Site. This technical support consists of computer modeling of the GCDF, design and emplacement of a Shallow Test Plot at NTS, and instrument testing at Los Alamos. Results to date on the computer modeling and the Shallow Test Plot are described

Mixed Waste Focus Area - Waste form initiative

International Nuclear Information System (INIS)

Nakaoka, R.; Waters, R.; Pohl, P.; Roach, J.

1998-01-01

The mission of the US Department of Energy's (DOE) Mixed Waste Focus Area (MWFA) is to provide acceptable technologies that enable implementation of mixed waste treatment systems which are developed in partnership with end-users, stakeholders, tribal governments, and regulators. To accomplish this mission, a technical baseline was established in 1996 and revised in 1997. The technical baseline forms the basis for determining which technology development activities will be supported by the MWFA. The primary attribute of the technical baseline is a set of prioritized technical deficiencies or roadblocks related to implementation of mixed waste treatment systems. The Waste Form Initiative (WFI) was established to address an identified technical deficiency related to waste form performance. The primary goal of the WFI was to ensure that the mixed low-level waste (MLLW) treatment technologies being developed, currently used, or planned for use by DOE would produce final waste forms that meet the waste acceptance criteria (WAC) of the existing and/or planned MLLW disposal facilities. The WFI was limited to an evaluation of the disposal requirements for the radioactive component of MLLW. Disposal requirements for the hazardous component are dictated by the Resource Conservation and Recovery Act (RCRA), and were not addressed. This paper summarizes the technical basis, strategy, and results of the activities performed as part of the WFI

The Basalt Waste Isolation Project technical program evaluation process: A criteria-based method

International Nuclear Information System (INIS)

Babad, H.; Evans, C.; Wolfe, B.A.

1982-01-01

The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the BWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (NWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP will be further formalized and further applied to the review of BWIP technical activities

Technical solutions for waste treatment in the Belene project

International Nuclear Information System (INIS)

Büttner, K.; Eichhorn, H.

2011-01-01

Outline: In June 2010 NUKEM Technologies GmbH was awarded a contract from ATOMSTROYEXPORT JSC to perform the complete work package related to designing and completion of the equipment for treatment of radioactive waste on the turn-key basis for Belene NPP. Technical Solutions: Waste Streams and Technologies at UKC and UKS; Concentration Plant; Thermal Treatment of Resins Sorting Facility; Biological Waste Water Treatment; Conditioning – Cementation • Sorting of Radwaste; Plasma Facility; Grouting; Filter Press; Monitoring and Tracking

Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing

Energy Technology Data Exchange (ETDEWEB)

Kelly, Steven E.

2013-11-11

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok's accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol.

Demonstrating Reliable High Level Waste Slurry Sampling Techniques to Support Hanford Waste Processing

International Nuclear Information System (INIS)

Kelly, Steven E.

2013-01-01

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HL W) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOC must demonstrate the ability to adequately mix and sample high-level waste feed to meet the WTP Waste Acceptance Criteria and Data Quality Objectives. The sampling method employed must support both TOC and WTP requirements. To facilitate information transfer between the two facilities the mixing and sampling demonstrations are led by the One System Integrated Project Team. The One System team, Waste Feed Delivery Mixing and Sampling Program, has developed a full scale sampling loop to demonstrate sampler capability. This paper discusses the full scale sampling loops ability to meet precision and accuracy requirements, including lessons learned during testing. Results of the testing showed that the Isolok(R) sampler chosen for implementation provides precise, repeatable results. The Isolok(R) sampler accuracy as tested did not meet test success criteria. Review of test data and the test platform following testing by a sampling expert identified several issues regarding the sampler used to provide reference material used to judge the Isolok's accuracy. Recommendations were made to obtain new data to evaluate the sampler's accuracy utilizing a reference sampler that follows good sampling protocol

Geotechnical support and topical studies for nuclear waste geologic repositories

International Nuclear Information System (INIS)

1990-12-01

This multidisciplinary project was initiated in fiscal year 1986. It comprises two major interrelated tasks, technical assistance and topical studies. The present report lists the technical reviews and comments made during the fiscal year 1989 and summarizes the technical progress of the topical studies. The major task was a study of the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses. In the area of technical assistance, there were a total of 30 geotechnical support activities, including reviews of 15 study plans (SP) and participation in 5 SP Review Workshops; in-depth multidisciplinary review of 5 Exploratory Shaft Facility (ESF) Study Plans and presentation of results to DOE; preparation and revision of a white paper and proposed work statement on preclosure monitoring and performance confirmation as an outgrowth of a request made by DOE to LBL; the hosting of a DOE program review; with DOE's encouragement, preparation of 8 papers for the International High-Level Radioactive Waste Management Conference to be held in April, 1990 in Las Vegas, Nevada; and 5 instances of general technical assistance to DOE

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package

Energy Technology Data Exchange (ETDEWEB)

Manaktala, H.K. (Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses); Interrante, C.G. (Nuclear Regulatory Commission, Washington, DC (USA). Div. of High-Level Waste Management)

1990-12-01

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig.

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package

International Nuclear Information System (INIS)

Manaktala, H.K.; Interrante, C.G.

1990-12-01

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide ''substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig

Selection of Technical Solutions for the Management of Radioactive Waste

International Nuclear Information System (INIS)

2017-07-01

The objectives of this publication are to identify and critically review the criteria to be considered while selecting waste management technologies; summarize, evaluate, rank and compare the different technical solutions; and offer a systematic approach for selecting the best matching solution. This publication covers the management of radioactive waste from all nuclear operations, including waste generated from research reactors, power reactors, and nuclear fuel cycle activities including high level waste (HLW) arising from reprocessing and spent nuclear fuel declared as waste (SFW), as well as low level waste (LLW) and intermediate level waste (ILW) arising from the production and use of radionuclides in industry, agriculture, medicine, education and research.

Separate collection of plastic waste, better than technical sorting from municipal solid waste?

Science.gov (United States)

Feil, Alexander; Pretz, Thomas; Jansen, Michael; Thoden van Velzen, Eggo U

2017-02-01

The politically preferred solution to fulfil legal recycling demands is often implementing separate collection systems. However, experience shows their limitations, particularly in urban centres with a high population density. In response to the European Union landfill directive, mechanical biological waste treatment plants have been installed all over Europe. This technology makes it possible to retrieve plastic waste from municipal solid waste. Operators of mechanical biological waste treatment plants, both in Germany and the Netherlands, have started to change their mechanical separation processes to additionally produce plastic pre-concentrates. Results from mechanical biological waste treatment and separate collection of post-consumer packaging waste will be presented and compared. They prove that both the yield and the quality of plastic waste provided as feedstock for the production of secondary plastic raw material are largely comparable. An economic assessment shows which conditions for a technical sorting plant are economically attractive in comparison to separate collection systems. It is, however, unlikely that plastic recycling will ever reach cost neutrality.

Support of the radioactive waste treatment nuclear fuel fabrication facility

International Nuclear Information System (INIS)

Park, H.H.; Han, K.W.; Lee, B.J.; Shim, G.S.; Chung, M.S.

1982-01-01

Technical service of radioactive waste treatment in Daeduck Engineering Center includes; 1) Treatment of radioactive wastes from the nuclear fuel fabrication facility and from laboratories. 2) Establishing a process for intermediate treatment necessary till the time when RWTF is in completion. 3) Technical evaluation of unit processes and equipments concerning RWTF. About 35 drums (8 m 3 ) of solid wastes were treated and stored while more than 130 m 3 of liquid wastes were disposed or stored. A process with evaporators of 10 1/hr in capacity, a four-stage solvent washer, storage tanks and disposal system was designed and some of the equipments were manufactured. Concerning RWTF, its process was reviewed technically and emphasis were made on stability of the bituminization process against explosion, function of PAAC pump, decontamination, and finally on problems to be solved in the comming years. (Author)

Evaluating the technical aspects of mixed waste treatment technologies

International Nuclear Information System (INIS)

Bagaasen, L.M.; Scott, P.A.

1992-10-01

This report discusses treatment of mixed wastes which is thought to be more complicated than treatment of either hazardous or radioactive wastes. In fact, the treatment itself is no more complicated: however, the regulations that define acceptability of the final waste disposal system are significantly more entangled, and sometimes in apparent conflict. This session explores the factors that influence the choice of waste treatment technologies, and expands on some of the limitations to their application. The objective of the presentation is to describe the technical factors that influence potential treatment processes and the ramifications associated with particular selections (for example, the generation of secondary waste streams). These collectively provide a framework for making informed treatment process selections

Technical support of standards for high-level radioactive waste management. Volume B. Engineering controls. Task b report Mar-Aug 77

International Nuclear Information System (INIS)

1979-01-01

This report is the result of work performed under the second part (Task B) of a four-part contract to gather technical information to evaluate enviornmental acceptablity of various options for disposing high-level wastes. The other tasks are: A-Source Term Characterization; C-Assessment of Migration Pathways; D-Assessment of Accidental Pathways. The scope of work for Task B was divided into 2 major steps: analysis of technology for engineering control of high-level wastes, and projections of costs for various alternative disposal technologies. Primary emphasis has been placed in non-reprocessed spent fuel. Brief consideration has been given to lower-level transuranic contaminated wastes which arise primarily from plutonium fuel fabrication and reprocessing plants. The objective of this limited review is to provide some insight into the state of the art for applying engineering controls to such wastes, including, where necessary, direct burial with high-level wastes in a geologic disposal facility

Technical justifications for the tests and criteria in the waste form technical position appendix on cement stabilization

International Nuclear Information System (INIS)

Siskind, B.; Cowgill, M.G.

1992-01-01

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes

Technical justifications for the tests and criteria in the waste form Technical position appendix on cement stabilization

International Nuclear Information System (INIS)

Siskind, B.; Cowgill, M.G.

1992-01-01

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix. Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test) especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guideline, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes. (author)

Technical career opportunities in high-level radioactive waste management

International Nuclear Information System (INIS)

1993-01-01

Technical career opportunities in high-level radioactive waste management are briefly described in the areas of: Hydrology; geology; biological sciences; mathematics; engineering; heavy equipment operation; and skilled labor and crafts

Solid Waste Burial Grounds/Central Waste Complex hazards assessment

International Nuclear Information System (INIS)

Broz, R.E.

1994-01-01

This document establishes the technical basis in support of Emergency Planning Activities for Solid Waste Burial Grounds/Central Waste Complex on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE Order 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is documented

ANL technical support program for DOE Environmental Restoration and Waste Management. Annual report, October 1991--September 1992

Energy Technology Data Exchange (ETDEWEB)

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J. [Argonne National Lab., IL (United States); Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L. [Lawrence Livermore National Lab., CA (United States); Ewing, R.C.; Wang, L. [Univ. of New Mexico, Albuquerque, NM (United States); Li, H.; Tomozawa, M. [Rensselaer Polytechnic Inst., Troy, NY (United States)

1993-05-01

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods.

Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

International Nuclear Information System (INIS)

1996-01-01

Much of the US Department of Energy's (DOE's) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL's main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers

Project Management Support and Services for the Environmental Restoration and Waste Management. Final report

International Nuclear Information System (INIS)

1995-01-01

The Los Alamos National Laboratory (LANL) Environmental Restoration Technical Support Office (ERTSO) contracted Project Time ampersand Cost, Inc. (PT ampersand C) on 16 November 1992 to provide support services to the US Department of Energy (DOE). ERTSO had traditionally supported the DOE Albuquerque office in the Environmental Restoration and Waste Management Programs and had also supported the Office of Waste Management (EM-30) at DOE Headquarters in Germantown, Maryland. PT ampersand C was requested to provide project management and support services for the DOE as well as liaison and coordination of responses and efforts between various agencies. The primary objective of this work was to continue LANL's technical support role to EM-30 and assist in the development of the COE Cost and Schedule Estimating (CASE) Guide for EM-30. PT ampersand C's objectives, as specified in Section B of the contract, were well met during the duration of the project through the review and comment of various draft documents, trips to DOE sites providing program management support and participating in the training for the EM-30 Cost and Schedule Estimating Guide, drafting memos and scheduling future projects, attending numerous meetings with LANL, DOE and other subcontractors, and providing written observations and recommendations.he results obtained were determined to be satisfactory by both the LANL ERTSO and DOE EM-30 organizations. The objective to further the support from LANL and their associated subcontractor (PT ampersand C) was met. The contract concluded with no outstanding issues

Treatment of solid wastes. Preventing waste production, recovery, waste collection, waste disposal, sanitation. Procedures, technical processes, legal foundations. 2. rev. ed. Behandlung fester Abfaelle. Vermeiden, Verwerten, Sammeln, Beseitigen, Sanieren. Verfahrensweise, technische Realisierung, rechtliche Grundlagen

Energy Technology Data Exchange (ETDEWEB)

Sattler, K.; Emberger, J.

1990-01-01

The book 'Treatment of Solid Wastes' was compiled by the group 'Environmental Protection/Waste Disposal' and looks at disposal methods and processes. The initial chapters deal with technical methods of environmental protection, describe laws and legal regulations pertaining to waste disposal, explain the quantities and composition of the waste matter and give an overview of the treatments which are available. Methods and technical process of waste collection, transport, sorting, recapturing of valuable matter, biochemical and thermal conversion and depositing. Treatment of poisonous wastes and old sites are dealt with in the final chapters. (orig./EF).

Technical requirements document for the waste flow analysis

International Nuclear Information System (INIS)

Shropshire, D.E.

1996-05-01

Purpose of this Technical Requirements Document is to define the top level customer requirements for the Waste Flow Analysis task. These requirements, once agreed upon with DOE, will be used to flow down subsequent development requirements to the model specifications. This document is intended to be a ''living document'' which will be modified over the course of the execution of this work element. Initial concurrence with the technical functional requirements from Environmental Management (EM)-50 is needed before the work plan can be developed

Engineering Technical Support Center (ETSC)

Science.gov (United States)

ETSC is EPA’s technical support and resource centers responsible for providing specialized scientific and engineering support to decision-makers in the Agency’s ten regional offices, states, communities, and local businesses.

Technical specifications for mechanical recycling of agricultural plastic waste

International Nuclear Information System (INIS)

Briassoulis, D.; Hiskakis, M.; Babou, E.

2013-01-01

Highlights: • Technical specifications for agricultural plastic wastes (APWs) recycling proposed. • Specifications are the base for best economical and environmental APW valorisation. • Analysis of APW reveals inherent characteristics and constraints of APW streams. • Thorough survey on mechanical recycling processes and industry as it applies to APW. • Specifications for APW recycling tested, adjusted and verified through pilot trials. - Abstract: Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project “LabelAgriWaste” revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process (“Quality I”) and another one for plastic profile production process (“Quality II”). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities

Technical specifications for mechanical recycling of agricultural plastic waste.

Science.gov (United States)

Briassoulis, D; Hiskakis, M; Babou, E

2013-06-01

Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project "LabelAgriWaste" revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process ("Quality I") and another one for plastic profile production process ("Quality II"). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities in protected cultivations in Europe. The adoption of the proposed specifications could transform this waste stream into a labelled commodity traded freely in the market and will constitute the base for the best economical and environmental valorisation of the APW. Copyright © 2013 Elsevier Ltd. All rights reserved.

Technical issues in the geologic disposal of radioactive wastes

International Nuclear Information System (INIS)

Weart, W.D.

1980-01-01

The status of technical understanding regarding radioactive waste repositories in geologic media is improving at a rapid rate. Within a few years the knowledge regarding non-salt repositories will be on a par with that which now exists for salt. To date there is no technical reason to doubt that geologic repositories in several different geologic media can be safely implemented to provide long-term isolation of radioactive wastes. Indeed, for bedded salt, there is now sufficient knowledge to allow all the identified phenomena to be bounded with satisfactory resultant consequences. It is possible to now proceed with technical confidence in an orderly development of a bedded-salt repository at a satisfactory site. This development would call for in-situ experiments, at the earliest possible stage, to confirm or validate the predictions made for the site. These in-situ experiments will be necessary for each repository in a different rock type. If, for non-technical reasons, repository development is delayed, field test facilities should be located as soon as possible in geologic settings typical of proposed repositories. Extensive testing to resolve generic issues will allow subsequent development of repositories to proceed more rapidly with only minimal in-situ testing required to resolve site-specific concerns

Compendium of technical computer codes used in support of the DOE Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

McBride, A.F.; Austin, P.N.; Ward, W.M.; McCarn, L.B.; Roddy, J.W.; Ludwig, S.B.; Reich, W.J.; Roussin, R.W.

1989-04-01

A compilation of technical computer codes related to ongoing work under the cognizance of the US Department of Energy's Office of Civilian Radioactive Waste Management (DOE/OCRWM) is presented. Much of the information was obtained from responses to a questionnaire distributed by DOE/OCRWM to all DOE offices associated with the radioactive waste management program. The codes are arranged alphabetically by name. In addition to the code description, each sheet includes other data such as computer hardware and software requirements, document references, name of respondent, and code variants. The codes are categorized into seventeen subject areas plus a miscellaneous category. Some of the subject areas covered are atmospheric dispersion, biosphere transport, geochemistry, nuclear radiation transport, nuclide inventory, and risk assessment. Three appendixes are included which list the names of the contributors, a list of the literature reviewed, and a glossary of computer code terminology and definitions. 50 refs., 3 tabs

Technical viability and development needs for waste forms and facilities

Energy Technology Data Exchange (ETDEWEB)

Pegg, I.; Gould, T.

1996-05-01

The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

2012-01-01

Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

Technical bases for leak detection surveillance of waste storage tanks. Revision 1

International Nuclear Information System (INIS)

Johnson, M.G.; Badden, J.J.

1995-01-01

This document provides the technical bases for specification limits, monitoring frequencies and baselines used for leak detection and intrusion (for single shell tanks only) in all single and double shell radioactive waste storage tanks, waste transfer lines, and most catch tanks and receiver tanks in the waste tank farms and associated areas at Hanford

Microbiological and technical aspects of anaerobic waste water purification

International Nuclear Information System (INIS)

Aivasidis, A.

1994-01-01

Anaerobic waste water purification is likely to be another example of how innovations can result from the joint use of biological and technical concepts. No matter how far the optimization of oxygen input with aerobic waste water purification advances it will still be the less a real competitor for anaerobic techniques the more polluted the waste water is. The principle of carrier fixation to avoid their washing out, too, has often been observed in nature with sessile microorganisms. With highly polluted water, anaerobic purification does not only work at no expenditure of energy but it can also make excess energy available for use in other processes. Another important argument for anaerobic methods of waste water purification is probably the clearly reduced production of excess sludge. (orig.) [de

Engineering Technical Support Center Annual Report Fiscal Year 2015

Science.gov (United States)

The United States Environmental Protection Agency (EPA or Agency) Office of Research and Development (ORD) created the Engineering Technical Support Center (ETSC) in 1987, one of several technical support centers created as part of the Technical Support Project (TSP). ETSC provid...

Balancing the technical, administrative, and institutional forces in defense waste management

International Nuclear Information System (INIS)

Hindman, T.B.

1988-01-01

Defense radioactive waste results from the Department of Energy's (DOE) national defense and nuclear weapons production activities. In 1983, the President submitted to Congress the Defense Waste Management Plan (DWMP) for defense high-level and transuranic wastes. The Plan proposed a workable approach for the final disposition of these wastes. The Department is still following the path laid out in this Plan. The proper management of this waste requires that technical, administrative, and institutional forces which are often neither well understood nor well documented be properly balanced. This paper clarifies the role these three forces play in the Defense waste management programs and provides examples of their impacts on specific programs

Nuclear Power Plant Temelin Technical Support Centre

International Nuclear Information System (INIS)

Krizek, K.

2000-01-01

The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

Waste management assessment and technical review programme. WATRP. An international peer review service for radioactive waste management activities

International Nuclear Information System (INIS)

1994-09-01

International Atomic Energy Agency provides international peer review services in radioactive waste management to those Member States that have established radioactive waste management programmes. Such services are provided within Waste Management Assessment and Technical Review Programme (WATRP). The main objective of WATRP is to provide international expertise and information on a requested subject in the field of radioactive waste management and to validate that programmes and activities are sound and performing well. Refs, figs and 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.

Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

International Nuclear Information System (INIS)

Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

2012-01-01

Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

ICT in supporting Nuclear Malaysia as National Technical Support Organization

International Nuclear Information System (INIS)

Saaidi Ismail; Siti Nurbahyah Hamdan; Mohd Fauzi Haris

2011-01-01

Information and communication technology (ICT) services are basic requirements in any organization during this information age. ICT is proven as a powerful enabler in organization due to its unique characteristics that improve communication, collaboration, and the exchange of information to strengthen and create new economic and social networks. As Malaysian Nuclear Agency is moving towards Technical Support Organization (TSO), the importance of ICT cannot simply be ignored. Being a TSO for national Nuclear Power Plant (NPP), Nuclear Malaysia is responsible for providing the technical and scientific basis for decisions and activities regarding nuclear technology and radiation safety. As a TSO, Nuclear Malaysia should utilize and collaborate data and information available from it activities and programs and use it to expedite the implementation of national NPP. Technical support also responsible to contribute an excellent operation by providing technical inputs and support for optimizing NPP component (such as plant procedures, operation and maintenance, technical assistance, training etc). These tasks can be performed more effectively and efficiently with the help of appropriate ICT services and solution. Therefore, the deployment and implementation of appropriate ICT requirement shall be made to fulfill agency needs. As initial step, existing ICT facilities should be reassessed. This is because the capacity of existing ICT services is very limited in terms of manpower, infrastructure, and applications. This paper however, will briefly discuss only to the requirement gap on existing ICT manpower and infrastructure with the requirement needed for TSO. The facts then will be used to improve ICT manpower and infrastructure in Nuclear Malaysia to provide reliable and high availability of technical support for national NPP. (author)

An analysis of the technical status of high level radioactive waste and spent fuel management systems

Science.gov (United States)

English, T.; Miller, C.; Bullard, E.; Campbell, R.; Chockie, A.; Divita, E.; Douthitt, C.; Edelson, E.; Lees, L.

1977-01-01

The technical status of the old U.S. mailine program for high level radioactive nuclear waste management, and the newly-developing program for disposal of unreprocessed spent fuel was assessed. The method of long term containment for both of these waste forms is considered to be deep geologic isolation in bedded salt. Each major component of both waste management systems is analyzed in terms of its scientific feasibility, technical achievability and engineering achievability. The resulting matrix leads to a systematic identification of major unresolved technical or scientific questions and/or gaps in these programs.

Models for waste life cycle assessment: Review of technical assumptions

DEFF Research Database (Denmark)

Gentil, Emmanuel; Damgaard, Anders; Hauschild, Michael Zwicky

2010-01-01

A number of waste life cycle assessment (LCA) models have been gradually developed since the early 1990s, in a number of countries, usually independently from each other. Large discrepancies in results have been observed among different waste LCA models, although it has also been shown that results...... from different LCA studies can be consistent. This paper is an attempt to identify, review and analyse methodologies and technical assumptions used in various parts of selected waste LCA models. Several criteria were identified, which could have significant impacts on the results......, such as the functional unit, system boundaries, waste composition and energy modelling. The modelling assumptions of waste management processes, ranging from collection, transportation, intermediate facilities, recycling, thermal treatment, biological treatment, and landfilling, are obviously critical when comparing...

Sampling and Analysis Plan for Tank 241-AP-108 Waste in Support of Evaporator Campaign 2000-1

International Nuclear Information System (INIS)

RASMUSSEN, J.H.

2000-01-01

This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AP-108 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000 and Von Bargen 1998) and 108-AP Tank Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Evaporator campaign 2000-1 will process waste from tank 241-AP-108 in addition to that from tank 241-AP-107. Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2000. No other needs (or issues) requiring data for this tank waste apply to this sampling event

Technical Advisory Committee on the nuclear fuel waste management program : thirteenth annual report

International Nuclear Information System (INIS)

Shemilt, L.W.

1993-03-01

Since the last reporting period by the Technical Advisory Committee (TAC) the emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of nine primary reference documents as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO). The disposal concept developed over the last fourteen years by Atomic Energy of Canada Limited (AECL) and anticipated to be presented by means of the EIS in 1994, is based on a multiple system of natural and man-made barriers wherein nuclear waste is first enclosed in corrosion-resistant containers, designed to last at least 500 years, and then placed in a vault excavated 500 - 1000 m deep in granitic rocks of the Canadian Shield. After container emplacement either in or on the floor of the vault, and with a surrounding buffer material of a bentonite clay/sand mixture, the vault will be backfilled and sealed with crushed rock, buffer and sand, as will be the shafts and exploratory boreholes. The case study being presented by AECL to demonstrate the safety of this concept and the technology to implement it, relies on computer simulations of a hypothetical disposal site with geological characteristics similar to those at the Underground Research Laboratory (URL) in the Whiteshell Research Area (WRA) located in Manitoba. The preliminary simulation results suggest that safe containment can be achieved provided that the waste is surrounded by a sparsely-fractured zone of rock wherein movement of contaminants carried by groundwater is modelled as a diffusive as opposed to a advective process. The principal focus of work during the past year within the environmental and safety assessment has been to complete the Post

Technical report from Radioactive Waste Management Funding and Research Center

International Nuclear Information System (INIS)

2007-10-01

As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

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).

NRC nuclear waste geochemistry 1983

International Nuclear Information System (INIS)

Alexander, D.H.; Birchard, G.F.

1984-05-01

The purpose of the meeting was to present results from NRC-sponsored research and to identify regulatory research issues which need to be addressed prior to licensing a high-level waste repository. Important summaries of technical issues and recommendations are included with each paper. The issue reflect areas of technical uncertainty addressed by the NRC Research program in geochemistry. The objectives of the NRC Research Program in geochemistry are to provide a technical basis for waste management rulemaking, to provide the NRC Waste Management Licensing Office with information that can be used to support sound licensing decisions, and to identify investigations that need to be conducted by DOE to support a license application. Individual papers were processed for inclusion in the Energy Data Base

Conclusions on the two technical panels on HLW-disposal and waste treatment processes respectively

International Nuclear Information System (INIS)

Dinkespiller, J.A.; Dejonghe, P.; Feates, F.

1986-01-01

The paper reports the concluding panel session at the European Community Conference on radioactive waste management and disposal, Luxembourg 1985. The panel considered the conclusions of two preceeding technical panels on high level waste (HLW) disposal and waste treatment processes. Geological disposal of HLW, waste management, safety assessment of waste disposal, public opinion, public acceptance of the manageability of radioactive wastes, international cooperation, and waste management in the United States, are all discussed. (U.K.)

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

Sustainable network of independent technical expertise for radioactive waste disposal (SITEX)

Energy Technology Data Exchange (ETDEWEB)

Serres, Christophe; Rocher, Muriel [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France); Bernier, Frederic [FANC, Brussels (Belgium); Havlova, Vaclava [UJV Rez, a.s., Rez (Czech Republic); Mrskova, Adela [DECOM A.S., Trnava (Slovakia); Dubreuil, Gilles Heriard [MUTADIS, Paris (France)

2013-07-01

SITEX is a 24 months FP7 Euratom project (from January 2012 to December 2013) led by IRSN and bringing together organisations representing technical safety organisations and nuclear safety authorities performing technical and scientific assessment of geological disposals for radioactive waste in the framework of their respective national regulatory review process of the safety case. Civil society outreach specialists of interaction with civil society are also involved in the project. SITEX aims at establishing the conditions required for developing sustainable interactions among experts from various horizons (nuclear safety authorities, technical safety organisations, civil society organisations..) capable of developing and coordinating joint and harmonized activities in relation with the safety assessment of the safety case. Among foreseen activities, partnership with the civil society experts is considered as a key function of the future network in order to contribute in enhancing trust in the decision making process. The SITEX program of work is split into a set of six workpackages that address technical and organizational issues allowing in fine to propose a structure of the activities and operating modes of the future network. These issues relate on the one hand to the study of the potential for sharing and developing technical expertise practices independently from the expertise developed by waste management organisations, on the other hand on the ability to implement coordinated R and D programs run by technical safety organisations in order to develop the scientific knowledge necessary to perform technical assessments. (orig.)

Management of radioactive waste at INR-technical support for processing of radioactive waste from nuclear facilities

International Nuclear Information System (INIS)

Bujoreanu, D.; Popescu, I.V.; Bujoreanu, L.

2009-01-01

The Institute for nuclear research (INR) subsidiary of the Romanian authority for nuclear activities has its own radwaste treatment plant (STDR). STDR is supposed to treat and condition radioactive waste from the nuclear fuel facility, the TRIGA reactor, post irradiation examination laboratories and other research laboratories of NRI. The main steps of waste processing are: pretreatment (collection, characterization, segregation, decontamination)., treatment (waste volume reduction, radionuclide removal, compositional change), conditioning (immobilization and containerization), interim storage of the packages in compliance with safety requirements for the protection of human health and environmental protection, transport of the packages containing radioactive waste, disposal.

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion

International Nuclear Information System (INIS)

Dyer, R.S.; Diamante, J.M.

1996-07-01

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility's capacity from 1,200 m 3 per year to 5,000 m 3 per year, will permit the facility to process high-salt wastes from the Russian Navy's Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted

Process Technical Basis Documentation Diagram for a solid-waste processing facility

International Nuclear Information System (INIS)

Benar, C.J.; Petersen, C.A.

1994-02-01

The Process Technical Basis Documentation Diagram is for a solid-waste processing facility that could be designed to treat, package, and certify contact-handled mixed low-level waste for permanent disposal. The treatment processes include stabilization using cementitious materials and immobilization using a polymer material. The Diagram identifies several engineering/demonstration activities that would confirm the process selection and process design. An independent peer review was conducted at the request of Westinghouse Hanford Company to determine the technical adequacy of the technical approach for waste form development. The peer review panel provided comments and identified documents that it felt were needed in the Diagram as precedence for Title I design. The Diagram is a visual tool to identify traceable documentation of key activities, including those documents suggested by the peer review, and to show how they relate to each other. The Diagram is divided into three sections: (1) the Facility section, which contains documents pertaining to the facility design, (2) the Process Demonstration section, which contains documents pertaining to the process engineering/demonstration work, and 3) the Regulatory section, which contains documents describing the compliance strategy for each acceptance requirement for each feed type, and how this strategy will be implemented

ERLN Technical Support for Labs

Science.gov (United States)

The Environmental Response Laboratory Network provides policies and guidance on lab and data requirements, Standardized Analytical Methods, and technical support for water and radiological sampling and analysis

Sampling and Analysis for Tank 241-AW-104 Waste in Support of Evaporator Campaign 2001-1

International Nuclear Information System (INIS)

MCKINNEY, S.G.

2000-01-01

This Tank Sampling and Analysis Plan (TSAP) identifies sample collection, laboratory analysis, quality assurance/quality control (QA/QC), and reporting objectives for the characterization of tank 241-AW-104 waste. Technical bases for these objectives are specified in the 242-A Evaporator Data Quality Objectives (Bowman 2000a and Von Bargen 1998), 242-A Evaporator Quality Assurance Project Plan (Bowman 1998 and Bowman 2000b), Tank 241-AW-104 Sampling Requirements in Support of Evaporator Campaign 2000-1 (Le 2000). Characterization results will be used to support the evaporator campaign currently planned for early fiscal year 2001. No other needs (or issues) requiring data for this tank waste apply to this sampling event

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 12. Repository preconceptual design studies: shale

International Nuclear Information System (INIS)

1978-04-01

This document describes a preconceptual design for a nuclear waste storage facility in shale. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/13, ''Drawings for Repository Preconceptual Design Studies: Shale.''

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 14. Repository preconceptual design studies: basalt

International Nuclear Information System (INIS)

1978-04-01

This document describes a preconceptual design for a nuclear waste storage facility in basalt. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/15, ''Drawings for Repository Preconceptual Design Studies: Basalt.''

Technical and Scientific Support Organizations Providing Support to Regulatory Functions. Companion CD-ROM

International Nuclear Information System (INIS)

2018-01-01

This publication introduces the general principles underlying the provision of technical and scientific support to a regulatory body and the characteristics of organizations providing such support. It describes the services provided to support regulatory functions as well as the associated activities and processes to maintain the needed level of expertise, state of the art tools and equipment. The publication is intended for use primarily by organizations that provide technical and scientific support in the field of nuclear and radiation safety. This also includes organizations that acquire such support, and regulatory bodies and governments, as they make decisions on the model of technical and scientific support to be developed at the national level, for example in the case of a country embarking on the development of a nuclear power programme. It is the first IAEA publication dedicated to the specific practices and challenges to be met by the technical and scientific support organizations. This CD-ROM includes the annexes to the printed publication of examples of TSOs and their interactions with key stakeholders.

Technical and logistic provisions for the delivery of radioactive wastes in the final repository Konrad

International Nuclear Information System (INIS)

Poeppinghaus, Jens

2013-01-01

The beginning of radioactive waste delivery to the final repository Konrad is planned for 2019. The main issue for the technical and logistic provisions is the development of a concept for the transport of the licensed radioactive waste containers to the site, including a turning concept for cylindrical waste forms and planning, construction and manufacture of transport equipment. Further issues include a logistic concept considering specific boundary conditions as administrative processes, priorities, special features of the delivering institutions and technical requirements of the repository.

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

International Nuclear Information System (INIS)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

Energy Technology Data Exchange (ETDEWEB)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

International Nuclear Information System (INIS)

1987-08-01

The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

Socio-technical systems analysis of waste to energy from municipal solid waste in developing economies: a case for Nigeria

Directory of Open Access Journals (Sweden)

Iyamu Hope O.

2017-01-01

Full Text Available Waste generation is an inevitable by-product of human activity, and it is on the rise due to rapid urbanisation, industrialisation, increased wealth and population. The composition of municipal solid waste (MSW in developed and developing economies differ, especially with the organic fraction. Research shows that the food waste stream of MSW in developing countries is over 50%. The case study for this investigation, Nigeria, has minimal formal recycling or resource recovery programs. The average composition of waste from previous research in the country is between 50–70% putrescible and 30–50% non-putrescible, presenting significant resource recovery potential in composting and biogas production. Waste-to-energy (WtE is an important waste management solution that has been successfully implemented and operated in most developed economies. This contribution reports the conditions that would be of interest before WtE potentials of MSW is harnessed, in an efficient waste management process in a developing economy like Nigeria. The investigation presents a set of socio-technical parameters and transition strategy model that would inform a productive MSW management and resource recovery, in which WtE can be part of the solution. This model will find application in the understanding of the interactions between the socio-economic, technical and environmental system, to promote sustainable resource recovery programs in developing economies, among which is WtE.

USACE AIS Transmit Technical Support Summary Report

Science.gov (United States)

2014-09-01

the TAG block for the correct transmitters, and then send to the USACE AIS network. B. Outbound openings in the USCG firewall for the USCG Message...USACE AIS Transmit Technical Support Summary Report Distribution Statement A: Approved for public release; distribution is unlimited...September 2014 Report No. CD-D-09-15 USACE AIS Transmit Technical Support Summary Report ii UNCLAS//Public | CG-926 RDC | I. Gonin et al. Public

Thirteenth annual report of the Technical Advisory Committee on the Nuclear Fuel Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

1993-05-15

This report details activities since the last reporting period by the Technical Advisory Committee (TAC). The emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of the primary reference document as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO).

Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

International Nuclear Information System (INIS)

1996-01-01

This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C.; Luna, R.E.; Jefferson, R.M.; Wowak, W.E.

1983-01-01

The Transportation Technology Center has been conducting a wide range of technical and non-technical research activities to assure the ability to transport radioactive materials in a safe, reliable, and publicly acceptable manner. These activities include tasks in Information and Intergovernmental issues, Safety Assessment and Environmental Analysis and Technology Development. Until recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on DOE for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Radioactive Waste Technical and Normative Aspects of its Disposal

CERN Document Server

Streffer, Christian; Kamp, Georg; Kröger, Wolfgang; Rehbinder, Eckard; Renn, Ortwin; Röhlig, Klaus-Jürgen

2012-01-01

Waste caused by the use of radioactive material in research, medicine and technologies, above all high level waste from nuclear power plants, must be disposed of safely. However, the strategies discussed for the disposal of radioactive waste as well as proposals for choosing a proper site for final waste disposal are strongly debated. An appropriate disposal must satisfy complex technical requirements and must meet stringent conditions to appropriately protect man and nature from risks of radioactivity over very long periods. Ethical, legal and social conditions must be considered as well. An interdisciplinary team of experts from relevant fields compiled the current status and developed criteria as well as strategies which meet the requirements of safety and security for present and future generations. The study also provides specific recommendations that will improve and optimize the chances for the selection of a repository site implementing the participation of stakeholders including the general public an...

The U.S. nuclear waste management program - technical progress at Yucca Mountain

Energy Technology Data Exchange (ETDEWEB)

Barrett, L.H. [U.S. Department of Energy (United States)

2001-07-01

This paper discusses the current status of a national program being developed by the U.S. Department of Energy for the management of spent nuclear fuel and high-level radioactive waste produced by civilian nuclear power generation and defense-related activities. In 1987 the U.S. Congress directed the Department to characterize the Yucca Mountain site in Nevada and determine its suitability for development of a geologic repository. This paper will focus on the technical progress that has been made after more than 15 years of scientific and engineering investigations at Yucca Mountain, and the remaining work that is being done to support a decision on whether to recommend the site for development of a geologic repository. (author)

Technical appraisal of the current situation in the field of radioactive waste management

International Nuclear Information System (INIS)

1985-01-01

Industrial activities are regarded as safe even though a small risk always exists. The philosophy of radiation protection accepts this and recognises that some level of risk will also be associated with safe radioactive waste management. Therefore the objective of radioactive waste management is to look for a strategy which, taken as a whole, is considered safe and provides an acceptable balance of all the radiological, technical, social, political and economic considerations. The RWMC's appraisal underlines the need for such a balance while concentrating on radiological and technical factors, particularly on the long term safety aspects of radioactive waste management. The fundamental conclusion is that detailed short and long term safety assessments can now be made which give confidence that radiation protection objectives can be met with currently available technology for most waste types, and at a cost which is only a small fraction of the overall cost of nuclear-generated power

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

Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

Energy Technology Data Exchange (ETDEWEB)

Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

1995-02-01

The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

International Nuclear Information System (INIS)

Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

1995-02-01

The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations

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

International Nuclear Information System (INIS)

Hagstrom, T.

1998-04-01

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

Waste Management Program. Technical progress report, July-December, 1984

International Nuclear Information System (INIS)

1986-10-01

This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement

Physico-chemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

International Nuclear Information System (INIS)

Mirsaidov, I.; Nazarov, K.

2014-01-01

Physico-chemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective site for reprocessing is Chkalovkst tailings wastes. The engineering and geological conditions and content of radionuclides in wastes were investigated. It was determined that considered by radioactivity the wastes are low activity and they can be reprocessed for the purpose of U_3O_8 production. Characteristics of mine and technical waters of uranium industry wastes were studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of SE “Vostokredmet” by classical methods of uranium leaching are studied. The kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk City) were also investigated. Further investigations are to reveal the flow mechanism process of sulfuric leaching of residues and to enable the selection of a radiation regime for U_3O_8 production. The kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes were studied. High sorption properties of apricot shell compared to other sorbents were revealed. A basic process flow diagram for reprocessing of uranium tailing wastes was developed as well as diagrams for uranium extraction from mine and technical waters from uranium industry wastes. The process consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration and drying. The possibility of uranium extraction from natural uranic waters of a complicated salt composition was considered. Investigations revealed that uranium extraction from brines containing chloride ion is possible. A developed uranium extraction scheme from Sasik-Kul lake’s brine consists of the following main stages: evaporation, leaching, chloride

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

A technical basis for meeting waste form stability requirements of 10 CFR 61

International Nuclear Information System (INIS)

Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

1988-01-01

To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

Effluent Management Facility Evaporator Bottom-Waste Streams Formulation and Waste Form Qualification Testing

Energy Technology Data Exchange (ETDEWEB)

Saslow, Sarah A.; Um, Wooyong; Russell, Renee L.

2017-08-02

This report describes the results from grout formulation and cementitious waste form qualification testing performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). These results are part of a screening test that investigates three grout formulations proposed for wide-range treatment of different waste stream compositions expected for the Hanford Effluent Management Facility (EMF) evaporator bottom waste. This work supports the technical development need for alternative disposition paths for the EMF evaporator bottom wastes and future direct feed low-activity waste (DFLAW) operations at the Hanford Site. High-priority activities included simulant production, grout formulation, and cementitious waste form qualification testing. The work contained within this report relates to waste form development and testing, and does not directly support the 2017 Integrated Disposal Facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY 2017 and future waste form development efforts. The provided results and data should be used by (1) cementitious waste form scientists to further the understanding of cementitious leach behavior of contaminants of concern (COCs), (2) decision makers interested in off-site waste form disposal, and (3) the U.S. Department of Energy, their Hanford Site contractors and stakeholders as they assess the IDF PA program at the Hanford Site. The results reported help fill existing data gaps, support final selection of a cementitious waste form for the EMF evaporator bottom waste, and improve the technical defensibility of long-term waste form risk estimates.

Scientific and technical basis for the near surface disposal of low and intermediate level waste

International Nuclear Information System (INIS)

2002-01-01

This report presents an overview of the scientific and technical basis for the disposal of low- and intermediate-level radioactive waste in near surface repositories. The focus is on basic principles, approaches, methodologies and technical criteria that can be used to develop and assess the performance of a disposal facility, and for building confidence in repository safety. This includes consideration of the multiple barrier concept, the performance of engineered barriers, the role of natural barriers and the development of a safety case. The emphasis is on defining the conditions relevant to the containment of the radionuclides in the repository and the processes that may affect the integrity of the engineered barriers. Both generic and specific data requirements for repository development and the assurance of safety are addressed. A large number of bibliographical references are given to support the information provided in this report

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

Scientific and technical challenges of radioactive waste management

International Nuclear Information System (INIS)

Vira, J.

1996-01-01

In spite of considerable spending on research and technical development, the management of nuclear wastes continues to be a difficult issue in public decision making. The nuclear industry says that it has safe solutions for the ultimate disposal of nuclear wastes, but the message has not really got through to the public at large. Although communications problems reflect the general stigmatization of nuclear power, there are obvious issues in safety and performance assessment of nuclear waste disposal which evade scientific resolution. Any scientist is concerned for his personal credibility must respect the rules and limits of scientific practice, but the intriguing question is whether he would not do better to address the layman's worries about radioactive substances? The discussion in this paper points out the intricacies of the distinction between scientific proof and judgement, with emphasis on safety assessment for nuclear waste disposal. Who are the final arbitrators? In a democratic society it is probably those who vote.Building confidence in expert judgements is a challenge for waste managers and scientists. The media may create their own 'experts', whose only necessary credential is the trust of their audience, but scientific judgements must stand the test of time.'Confidence building' is currently a key word on the whole nuclear waste management scene, and confidence in science and scientists is certainly needed for any progress towards practical implementation of plans. The means for building confidence in the decision-making process are probably different from those applied for science and scientists. (author)

OPG Western Waste Management Facility

Energy Technology Data Exchange (ETDEWEB)

Julian, J. [Ontario Power Generation, Western Waste Management Facility, Tiverton, ON (Canada)

2011-07-01

The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)

OPG Western Waste Management Facility

International Nuclear Information System (INIS)

Julian, J.

2011-01-01

The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)

Communication of technical information to lay audiences. [National Waste Terminal Storage (NWTS) program

Energy Technology Data Exchange (ETDEWEB)

Bowes, J.E.; Stamm, K.R.; Jackson, K.M.; Moore, J.

1978-05-01

One of the objectives of the National Waste Terminal Storage (NWTS) Program is to provide terminal storage facilities for commercial radioactive wastes in various geologic formations at multiple locations in the United States. The activities performed under the NWTS Program will affect regional, state, and local areas, and widespread public interest in this program is expected. Since a large part of the NWTS Program deals with technical information it was considered desirable to initiate a study dealing with possible methods of effectively transmitting this technical information to the general public. This study has the objective of preparing a state-of-the-art report on the communication of technical information to lay audiences. The particular task of communicating information about the NWTS Program to the public is discussed where appropriate. The results of this study will aid the NWTS Program in presenting to the public the quite diverse technical information generated within the program so that a widespread, thorough public understanding of the NWTS Program might be achieved. An annotated bibliography is included.

Criteria and technical concept for demonstrating greater confinement disposal of radioactive wastes at Arid Western Sites

International Nuclear Information System (INIS)

Hunter, P.H.

1981-01-01

This report summarizes the work of two documents; the Criteria for Greater Confinement of Radioactive Wastes at Arid Western Sites, NVO-234, March 1981, (within this report, referred to as the GCDF Criteria Document); and the Draft Technical Concept for a Test of Greater Confinement Disposal of Radioactive Waste in Unsaturated Media at the Nevada Test Site, FBDU-343-004, June 1981, (referred within this report as the Technical Concept for the GCDF). For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in development of defense low-level waste management concepts, including the greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which we published in May of this year; then the draft for the technical concept for greater confinement disposal, published in June; leading up to the point where we are now. The final technical concept and design specifications should be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year

The technical support organization at BNL is twenty years old

International Nuclear Information System (INIS)

Indusi, J.P.

1988-01-01

The Technical Support Organization was established by the Atomic Energy Commission in January 1968 at Brookhaven National Laboratory (BNL). The original idea came from a small group of scientists at BNL. The group included Willy Higinbotham, Herb Kouts, Frank Miles, Richard Dodson, and Gerhardt Friedlander. The AEC endorsed the idea of a technical support group to provide technical assistance to AEC's Office of Safeguards and Materials Management and they sent requests for expressions of interest throughout the complex. For a number of reasons, to be discussed in the paper, the Technical Support Organization was established at BNL. An early project was the Conceptual Design for Safeguarding Nuclear Material which formed the first logical and systematic description of the integration of several elements into a safeguards system for protecting nuclear materials. Many other projects were undertaken over the years. TSO today provides technical assistance to the DOE Office of Safeguards and Secuirty, the Office of Classification and Technology Policy, and the Office of Security Evaluations. Technical support to the IAEA is provided under the Program of Technical Assistance to Agency Safeguards (POTAS). Recently, TSO began a program of technical assistance to the Air Force Weapons Laboratory in the area of nuclear systems security

Technology development activities supporting tank waste remediation

International Nuclear Information System (INIS)

Bonner, W.F.; Beeman, G.H.

1994-06-01

This document summarizes work being conducted under the U.S. Department of Energy's Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation

Technical requirements for the actinide source-term waste test program

Energy Technology Data Exchange (ETDEWEB)

Phillips, M.L.F.; Molecke, M.A.

1993-10-01

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

Technical requirements for the actinide source-term waste test program

International Nuclear Information System (INIS)

Phillips, M.L.F.; Molecke, M.A.

1993-10-01

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency's 40 CFR Part 191B

Technical support for universal health coverage pilots in Karnataka ...

International Development Research Centre (IDRC) Digital Library (Canada)

Technical support for universal health coverage pilots in Karnataka and Kerala. This project will provide evidence-based support to implement universal health coverage (UHC) pilot activities in two Indian states: Kerala and Karnataka. The project team will provide technical assistance to these early adopter states to assist ...

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

International Nuclear Information System (INIS)

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

Radioactive-waste isolation pilot plant

International Nuclear Information System (INIS)

Weart, W.D.

1977-01-01

The objective of the Waste Isolation Pilot Plant (WIPP) program is to demonstrate the suitability of bedded salt, specifically, the bedded salt deposits in the Los Medanos area of southeastern New Mexico, as a disposal medium for radioactive wastes. Our program responsibilities include site selection considerations, all aspects of design and development, technical guidance of facility operation, environmental impact assessment, and technical support to ERDA for developing public understanding of the facility

Method for assessment of the technical potential of the plant agricultural waste suitable for energy purposes in Bulgaria

International Nuclear Information System (INIS)

Georgiev, V.

2004-01-01

A method for assessment of technical potential of quantitatively important plant agriculture waste; straw from wheat and barley; corn stalks; sunflower stalks and heads; tobacco stalks; orchard prunings and vineyard prunings suitable for energy purposes for Bulgarian conditions is developed. Data for assessment of the technical potential for 2002 using this method are presented. A comparison between technical potential of mentioned wastes, final energy consumption in agriculture and all branches of Bulgarian economy for 2002 is made. (author)

The management of radioactive wastes produced by radioisotope users. Technical addendum

International Nuclear Information System (INIS)

1966-01-01

This Addendum contains detailed technical information on processes and procedures that are outlined in more general terms in the Code of Practice. The information is particularly relevant to the problem of handling the relatively small quantities of waste arising from the use of radionuclides in laboratories, hospitals and industry when no special facilities for radioactive waste treatment are available on site. The Addendum is directed toward providing the radioisotope user with the type and amount of information required for him to be able to assess the alternatives available to him in terms of his particular needs, develop a preliminary design of an optimum waste-handling system and get help and guidance in his search for more detailed information.

(Technical and engineering support for the Office of Industrial Programs)

Energy Technology Data Exchange (ETDEWEB)

1991-01-01

As of April 19, 1991, technical, operational and analytic support and assistance to the offices and divisions of the Office of Renewable Energy, under contract DE-AC01-86CE30844 was completed. The overall work effort, initiated February 20, 1986, was characterized by timely, comprehensive, high quality, professional responsiveness to a broad range of renewable energy program operational support requirements. These are no instances of failure to respond, nor unacceptable response, during the five-year period. The technology program areas covered are Solar Buildings Technology, Wind Energy Technology, Photovoltaic Energy Technology, Geothermal Energy Technology, Biofuels and Municipal Waste Technology, Solar Thermal Technology, Hydropower Energy Technology, Ocean Energy Technology, and Electric Energy Systems and Energy Storage. The analytical and managerial support provided to the office and staff of the Deputy Assistant Secretary for Renewable Energy enabled a comprehensive evaluation of program and policy alternatives, and the selection and execution of appropriate courses of action from amongst those alternatives. Largely through these means the Office has been able to maintain continuity and a meaningful program thrust through the vacillations of policies and budgets that it has experienced over that it has experienced over the past five years. Appended are summaries of support activities within each of the individual technology program areas, as well as a complete listing of all project deliverables and due-dates for each submittal under the contract.

[Technical and engineering support for the Office of Industrial Programs

International Nuclear Information System (INIS)

1991-01-01

As of April 19, 1991, technical, operational and analytic support and assistance to the offices and divisions of the Office of Renewable Energy, under contract DE-AC01-86CE30844 was completed. The overall work effort, initiated February 20, 1986, was characterized by timely, comprehensive, high quality, professional responsiveness to a broad range of renewable energy program operational support requirements. These are no instances of failure to respond, nor unacceptable response, during the five-year period. The technology program areas covered are Solar Buildings Technology, Wind Energy Technology, Photovoltaic Energy Technology, Geothermal Energy Technology, Biofuels and Municipal Waste Technology, Solar Thermal Technology, Hydropower Energy Technology, Ocean Energy Technology, and Electric Energy Systems and Energy Storage. The analytical and managerial support provided to the office and staff of the Deputy Assistant Secretary for Renewable Energy enabled a comprehensive evaluation of program and policy alternatives, and the selection and execution of appropriate courses of action from amongst those alternatives. Largely through these means the Office has been able to maintain continuity and a meaningful program thrust through the vacillations of policies and budgets that it has experienced over that it has experienced over the past five years. Appended are summaries of support activities within each of the individual technology program areas, as well as a complete listing of all project deliverables and due-dates for each submittal under the contract

Nordic study on reactor waste. Technical part 1 and 2

International Nuclear Information System (INIS)

1981-08-01

An important part of the Nordic studies on system- and safety analysis of the management of low and medium level radioactive waste from nuclear power plants, is the safety analysis of a Reference System. This reference system was established within the study and is described in this Technical Part 1. The reference system covers waste management Schemes that are potential possibilities in either one of the four participating Nordic countries. The reference system is based on: a power reactor system consisting of 6 BWR's of 500 MWe each, operated simultaneously over the same 30 year period, and deep bed granular ion exchange resin wastes from the Reactor Water Clean-Up System (RWCS and powdered ion exchange resin from the Spent Fuel Pool Cleanup System (SFPCS)). Both waste types are supposed to be solidified by mixing with cement and bitumen. Two basic types of containers are considered. Standard 200 liter steel drums and specially made cubicreinforced concrete moulds with a net volume of 1 m 3 . The Nordic study assumes temporary storage of the solidified waste for a maximum of 50 years before the waste is transferred to the disposal site. Transportation of the waste from the storage facilitiy to the disposal site will be by road or sea. Three different disposal facilities are considered: Shallow land burial, near surface concrete bunker, and rock cavern with about 30 m granite cover. (EG)

Nordic study on reactor waste. Technical part 3

International Nuclear Information System (INIS)

1981-08-01

The ground disposal alternatives examined in the Nordic study are based on establishment of relevant product specifications which can be adapted to the safety analysis of the entire waste handling sequence. Such product specifications would in turn influence the choice of incorporation techniques and may enable an optimization of the process. In order to interprete the small-scale laboratory tests with respect to long-term performance of full-scale products there were accomplished: - qualitative evaluations of the relevance of product properties for normal and abnormal events during storage, transport and disposal; - attempts to quantify the relevance of different properties, i.e. their influence on radiation doses from different stages of well specified waste management system; - assessments of available laboratory tests and of correlations between results from such tests and the long-term performance of full-scale technical products; - studies of reaction mechanisms and parameters that can affect the long-term performance of disposed products; - laboratory incorporation experiments to study impacts of process variables on the fixation of ion exchange wastes in cement and bitumen; - full-scale tests to study product performance under simulated accident conditions. (EG)

Activities of the IAEA in the area of radioactive waste management

International Nuclear Information System (INIS)

Efremenkov, V.M.

1998-01-01

The IAEA activity in the area of radioactive waste management mainly concentrates on three areas, namely: (i) the establishing of international principles and standards for the safe management of radioactive waste; (ii) to promote the development and improvements of waste processing technologies, including handling, treatment, conditioning, packaging, storage and disposal of waste; and (iii) assisting developing Member States in establishing good waste management practice through dissemination of technical information, providing technical support and training. These activities are carried out by the Waste Technology Section, Department of Nuclear Energy, and the Waste Safety Section, Department of Nuclear Safety. The Waste Technology Section's activities are organized into four subprogrammes covering: the handling, processing and storage of radioactive waste; radioactive waste disposal; technology and management aspects of decontamination, decommissioning and environmental restoration; and waste management information and support services

Technical Support and Transfer of Geothrmal Technical Knowledge and Information

Energy Technology Data Exchange (ETDEWEB)

John W. Lund; Toni" Boyd

2007-11-14

The Geo-Heat Center (GHC) staff provided responses to 1442 technical support requests during the contract period (April 1, 2006 to September 30, 2007), which were six quarters under this contract. Our website, consisting of 1900 files, also contributes to our technical assistance activity. Downloaded files were 1,889,323 (3,448 per day) from our website, the total number of users was 1,365,258 (2,491 per day), and the total number of hits were 6,008,500 (10,064 per day). The GHC staff attended 60 workshops, short course and professional meeting and made 29 technical presentations. The staff also prepared and mailed out 2,000 copies of each of five issues of the GHC Quaterly Bulletin which contained 26 articles. We also mailed out approximately 5,000 papers and publications to interested individuals and organizations.

Process waste assessment approach, training and technical assistance for DOE contractors

International Nuclear Information System (INIS)

Pemberton, S.

1994-03-01

The Department of Energy (DOE) and its contractors are faced with a large waste management problem as are other industries. One of the tools used in a successful waste minimization pollution prevention (WMin/P2) program is a process waste assessment (PWA). The purpose of this project was to share the Kansas City Plant's (KCP's) PWA expertise with other DOE personnel and DOE contractors. This consisted of two major activities: (1) The KCP's PWA graded approach methodology was modified with the assistance of DOE/Defense Program's laboratories, and (2) PWA training and technical assistance were provided to interested DOE personnel and DOE contractors. This report documents the FY93 efforts, lesson learned, and future plans for both PWA-related activities

Technical approach for the management of UMTRA ground water investigation-derived wastes

International Nuclear Information System (INIS)

1994-02-01

During characterization, remediation, or monitoring activities of the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project, ground water samples are collected to assess the extent and amount of waterborne contamination that might have come from the mill tailings. This sampling sometimes occurs in contaminated areas where ground water quality has been degraded. Ground water sampling activities may result in field-generated wastes that must be disposed of in a manner protective of human health and the environment. During ground water sampling, appropriate measures must be taken to dispose of presampling purge water and well development water that is pumped to flush out any newly constructed wells. Additionally, pumping tests may produce thousands of gallons of potentially contaminated ground water that must be properly managed. In addition to the liquid wastes, there is the potential for bringing contaminated soils to the ground surface during the drilling and installation of water wells in areas where the subsurface soils may be contaminated. These soils must be properly managed as well. This paper addresses the general technical approach that the UMTRA Project will follow in managing field-generated wastes from well drilling, development, sampling, and testing. It will provide guidance for the preparation of Technical Assistance Contractor (TAC) Standard Operating Procedures (SOP) for the management and disposal of field-generated wastes from ground water monitoring and remediation activities

Reflecting socio-technical combinations in radioactive waste management. Results from the InSOTEC European research project

International Nuclear Information System (INIS)

Kallenbach-Herbert, Beate; Bergmans, Anne; Martell, Meritxell; Schroeder, Jantine

2015-01-01

InSOTEC is a three-year collaborative social sciences research project funded under the European Atomic Energy Community's 7th Framework Programme FP7. The project aims to generate a better understanding of the complex interplay between the technical and the social in the context of geological disposal of radioactive waste. In doing so, InSOTEC has moved beyond the social and technical division that is frequently being found in this context by - investigating the consideration of social sciences and the recognition of socio-technical combinations in research programs on geological disposal, - analyzing the socio-technical entanglement in selected contexts like siting, reversibility and retrievability, demonstrating safety and technology transfer on the basis of case studies, and - exploring the integration of diverse stakeholders in technology oriented networks. The analyses reveal that activities in the context of geological disposal, whether related to research, planning, siting etc., rather support the divide of social and technical aspects than fostering the consideration of their entanglement. Reasons identified for this are manifold. The wish to reduce complexity by focusing stakeholder involvement on social questions and fixing the technical part ''when acceptance is reached'' is only one of them. However, the analyses also show that over the long timescales of repository planning and implementation, robust management strategies must provide the flexibility to adapt to both technical and social developments and demands. Understanding the socio-technical interplay and creating structures for its consideration provides the basis for dealing with this challenge. This presentation will focus on the main findings of the InSOTEC project with regard to the consideration of socio-technical combinations in practice. These insights are currently under development and will be finalized at the end of the project in June 2014. We will reflect on

Reflecting socio-technical combinations in radioactive waste management. Results from the InSOTEC European research project

Energy Technology Data Exchange (ETDEWEB)

Kallenbach-Herbert, Beate [Oeko-Institut e.V., Darmstadt (Germany); Bergmans, Anne [Antwerp Univ. (Belgium); Martell, Meritxell [Merience Strategic Thinking, Olerdola (Spain); Schroeder, Jantine [Antwerp Univ. (Belgium); SCK - CEN, Mol (Belgium)

2015-07-01

InSOTEC is a three-year collaborative social sciences research project funded under the European Atomic Energy Community's 7th Framework Programme FP7. The project aims to generate a better understanding of the complex interplay between the technical and the social in the context of geological disposal of radioactive waste. In doing so, InSOTEC has moved beyond the social and technical division that is frequently being found in this context by - investigating the consideration of social sciences and the recognition of socio-technical combinations in research programs on geological disposal, - analyzing the socio-technical entanglement in selected contexts like siting, reversibility and retrievability, demonstrating safety and technology transfer on the basis of case studies, and - exploring the integration of diverse stakeholders in technology oriented networks. The analyses reveal that activities in the context of geological disposal, whether related to research, planning, siting etc., rather support the divide of social and technical aspects than fostering the consideration of their entanglement. Reasons identified for this are manifold. The wish to reduce complexity by focusing stakeholder involvement on social questions and fixing the technical part ''when acceptance is reached'' is only one of them. However, the analyses also show that over the long timescales of repository planning and implementation, robust management strategies must provide the flexibility to adapt to both technical and social developments and demands. Understanding the socio-technical interplay and creating structures for its consideration provides the basis for dealing with this challenge. This presentation will focus on the main findings of the InSOTEC project with regard to the consideration of socio-technical combinations in practice. These insights are currently under development and will be finalized at the end of the project in June 2014. We will reflect on

Infrastructure support for the Waste Management Institute. Progress report

International Nuclear Information System (INIS)

1995-01-01

North Carolina A ampersand T State University is in the process of developing an infrastructure for an interdisciplinary Waste Management Institute (WMI). The Interdisciplinary Waste Management Institute (WMI) was approved in June 1994 by the General Administration of the University of North Carolina as an academic support unit with research and public service functions. The mission of the WMI is to enhance awareness and understanding of waste management issues and to provide instructional support including research and outreach. The goals of WMI are as follows: increase the number of minority professionals who will work in waste management fields; develop cooperative and exchange programs involving faculty, students, government, and industry; serve as institutional sponsor of public awareness workshops and lecture series; and support interdisciplinary research programs. Accomplishments for this reporting period are presented for WMI enrollment; waste management and certificate program; waste management instructional projects; undergraduate scholarship/stipend and faculty student development projects; research; and community relations

Logistic management materials-technical support railway enterprises

OpenAIRE

Dykan, V.; Borozenetc, T.

2014-01-01

The essence of logistics management. Determine the feasibility of applying the principles of logistics management in organizing the logistics of railway transport. Discussed measures to develop suppliers in the implementation of logistics management logistics. Identified the need to develop and implement regulatory and methodical system to improve materials-technical support through the introduction of modern logistics principles. Applied systemic campaign to organize the materials-technical ...

The Michigan high-level radioactive waste program: Final technical progress report

International Nuclear Information System (INIS)

1987-01-01

This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

Technical performance characterization of fourier transform profilometry for quantitative waste volume determination under Hanford waste tank conditions - 16281

International Nuclear Information System (INIS)

Monts, David L.; Jang, Ping-Rey; Long, Zhiling; Norton, Olin P.; Gresham, Lawrence L.; Su, Yi; Lindner, Jeffrey S.

2009-01-01

The Hanford Site in western Washington state is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing an quantitative in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. We have initiated a technical feasibility assessment of the Fourier transform profilometry (FTP) technique for determining the volume of residual waste in Hanford radioactive waste tanks; preliminary results to date are presented in this paper. We find that we achieve FTP volume determinations with relatively small errors under conditions corresponding to the most challenging within a Hanford waste tank-viewing non-descript targets at a distance of 16.1 m (53 ft) and an angle of 62 deg.. We have determined that we can minimize measurement uncertainty by maximizing the camera-to-projector distance d, using an optical zoom of at least 5x, and ensuring that FTP images are only recorded after instrumental warm

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 20. Thermo-mechanical stress analysis and development of thermal loading guidelines

International Nuclear Information System (INIS)

1978-04-01

This volume is one of a 23-volume series which supplements a Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel, and uranium-only recycling. The thermo-mechanical analysis of proposed preconceptual repositories in granite, shale and basalt have been undertaken. The analysis, was conducted on three different levels of scale (i) Very Near Field (canister scale), (ii) Near Field (excavation scale) and (iii) Far Field (regional scale) studies. Three numerical methods were used to undertake the thermo-mechanical calculations; namely, the finite element method for thermal stress analysis, the boundary element method for thermal and thermal stress analysis and the semi-analytical method also for thermal and thermal stresses analysis. From the thermo-mechanical studies with simplifying assumptions on rock mass behavior where applicable, recommendations for areal thermal loadings to assure retrievability of the canisters and long term safety of the repository are given

Waste management at Los Alamos: Protecting our environment

International Nuclear Information System (INIS)

1993-01-01

This report consists of a broad overview of activities at Los Alamos National Laboratory (LANL). The following topics are discussed: The growth of the waste management group; what we do today; the mission of the waste management group; the liquid waste treatment section; the radioactive liquid waste project office; the chemical waste section; the radioactive waste section; and the technical support section

Waste management at Los Alamos: Protecting our environment

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This report consists of a broad overview of activities at Los Alamos National Laboratory (LANL). The following topics are discussed: The growth of the waste management group; what we do today; the mission of the waste management group; the liquid waste treatment section; the radioactive liquid waste project office; the chemical waste section; the radioactive waste section; and the technical support section.

Report: Searching for a way to sustainability: technical and policy analyses of solid waste issues in Kathmandu.

Science.gov (United States)

Dangi, Mohan B; Cohen, Ronald R H; Urynowicz, Michael A; Poudyal, Khem N

2009-05-01

Kathmandu Metropolitan City has attempted to reorganize its solid waste management a number of times. The German Technical and Financial Aid Organization led early efforts that were followed by a number of more recent experiments that left the city with an unsustainable solid waste management system following the termination of foreign aid. To examine this failure, the research team evaluated household surveys, field observations, interviews, and other primary and secondary information within the context of technical, social, and institutional analyses. The survey results show that the solid waste collection rates are far below the 90% claimed by the metropolis and street sweeping consumes approximately 51% of its solid waste budget. As a result of the relatively low collection rates the city residents are encouraged to dump waste into public lands. Consequently, too much of the city's resources are focused on sweeping rather than collection. Kathmandu needs to recognize informal waste picking, privatize, use local techniques, build capacity, promote bottom-up and participatory styles of management, and regulate policies to maintain solid waste management.

Nuclear waste management technical support in the developmnt of nuclear waste form criteria for the NRC. Task 5. National waste package program

International Nuclear Information System (INIS)

Davis, M.S.

1982-02-01

This report assesses the need for a centrally organized waste package effort and whether the present national program meets those needs. It is the conclusion of the BNL staff that while the DOE has in principle organized a national effort to develop high-integrity waste packages for geologic disposal of high level waste, the effort has not yet produced data to demonstrate that a waste package will comply with NRC's criteria. The BNL staff feels, however, that such a package is achievable either by development of high integrity components which by themselves could comply with 1000-year containment or by the development of new waste package designs that could comply with both the containment and the controlled release criteria in the 10CFR 60 performance objectives. In terms of waste forms, high-integrity components such as pyrolytic carbon coated waste and radioactive glass coated with non-radioactive glass offer higher potential than normal borosilicate waste glass. The existing container research program has yet to produce the data base on which to assess the potential of a container material to contain the waste for 1000 years. However, there may be the potential, based on Swedish calculations and work done on titanium in the DOE program, that Ti or its alloys may satisfy this criterion. Existing data on natural backfills will not be acceptable as the sole source for satisfying containment and the long-term release rate criteria. However, a synthetic zeolite system is an example of a backfill with a potential to satisfy both criteria. In this particular case, it is the BNL staff's opinion that existing technology and data for this system indicate that major development programs may not be required to qualify this material for licensing applications. The most likely means available for satisfying 10 CFR 60 with a single package component is through the performance of a discrete backfill

Technical, normative and social aspects of the site selection process for radioactive waste repositories

International Nuclear Information System (INIS)

Branco, Otavio E.A.; Rodrigues, Paulo C.H.; Carvalho Filho, Carlos A.; Cota, Stela D.S.; Ferreira, Vinicius V.M.; Peres, Sueli S.; Hiromoto, Goro

2009-01-01

In force since 2001, the Federal Law 10.308 states, in article 37, that the Comissao Nacional de Energia Nuclear - CNEN should start studies for the implementation of a final radioactive waste repository, 'in the shortest timeframe technically feasible'. Nevertheless, not only technical aspects have to be taken into account to accomplish with this schedule, but, also factors of political, economic and social nature. In this paper, the importance and impact of public acceptance aspects are discussed, as well as the methodology of site selection for radioactive wastes repositories, and proposals to accommodate the emanated criteria from the existing legislation. Additionally, practical results from the international experience in the implementation of such deposits are presented. (author)

Technical soaps - a possibility of decontaminating thorium-contaminated waste waters

International Nuclear Information System (INIS)

Drathen, H.; Erichsen, L. v.

1977-01-01

Thorium-contaminated waste waters showing a concentration of thorium higher than 10sup(-5) mol/l can be quantitatively decontaminated by adding soaps. Concentrations of impurity ions of both tap and sea waters have been taken into consideration. As there is no difference between soaps and soap mixtures concerning the quantity of precipitation rates, technical soaps are from the economic point of view best suited for decontaminating thorium-contaminated waste waters. Having a soap concentration of 200% of the stoichiometric amount of thorium and a concentration of impurity ions of 10sup(-2) mol/l, it is assumed that decontamination factors of more than 20 can be reached in one step. (orig.) [de

Needs, requirements and challenges for technical support to nuclear safety authority

International Nuclear Information System (INIS)

Madonna, A.; Orsini, G.

2010-01-01

To face the very broad range of technical matters on which the regulatory and licensing activity are based, and related research and development activity, the Nuclear Safety Authorities (NSA) may need to rely upon external technical and scientific support. In providing technical support to NSA, the experience shows, from one side, the importance to have technical support organizations (TSO) with recognized competence, independence and appropriate regulatory view, and from the other side, the importance to have within the NSAs well developed management and technical capability to address, coordinate and use the results of the external technical support. Retaining the NSA the full responsibility for the final decision. Under which conditions and modus operandi the external support shall be provided in order to comply with requirements of being independent, competent and timely provided, fulfilling the administrative procedures, is the subject of attention and consideration of TSO function today. The Italian regulatory body is currently going to be institutionally re-established according to new law approved in 2009 /1/ and it needs to be resourced and fully organized with necessary capacities in the nearest future. The perspective of a new nuclear program, recently launched by the government, with significant incoming tasks for regulation and licensing, against the existing limited resources, let foresee a substantial potential need for technical support and advice. ITER-Consult (Ltd), created in 2003 in Italy, has well developed capabilities to provide independent technical evaluation and support to NSAs, to maintain safety culture and updated knowledge, to transfer know how and to establish international cooperation and networking. This mission is guided assuming as values the independence, the professional competence, the transparency, the credibility and the establishment of respectful relationship with the partners. Challenges exist for funding and operational

A web-based Decision Support System for the optimal management of construction and demolition waste.

Science.gov (United States)

Banias, G; Achillas, Ch; Vlachokostas, Ch; Moussiopoulos, N; Papaioannou, I

2011-12-01

Wastes from construction activities constitute nowadays the largest by quantity fraction of solid wastes in urban areas. In addition, it is widely accepted that the particular waste stream contains hazardous materials, such as insulating materials, plastic frames of doors, windows, etc. Their uncontrolled disposal result to long-term pollution costs, resource overuse and wasted energy. Within the framework of the DEWAM project, a web-based Decision Support System (DSS) application - namely DeconRCM - has been developed, aiming towards the identification of the optimal construction and demolition waste (CDW) management strategy that minimises end-of-life costs and maximises the recovery of salvaged building materials. This paper addresses both technical and functional structure of the developed web-based application. The web-based DSS provides an accurate estimation of the generated CDW quantities of twenty-one different waste streams (e.g. concrete, bricks, glass, etc.) for four different types of buildings (residential, office, commercial and industrial). With the use of mathematical programming, the DeconRCM provides also the user with the optimal end-of-life management alternative, taking into consideration both economic and environmental criteria. The DSS's capabilities are illustrated through a real world case study of a typical five floor apartment building in Thessaloniki, Greece. Copyright © 2011 Elsevier Ltd. All rights reserved.

Development of technical design for waste processing and storage facilities for Novi Han repository

International Nuclear Information System (INIS)

Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

2005-01-01

Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

International Nuclear Information System (INIS)

Duncan, Garth M.; Saunders, Scott A.

2013-01-01

The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

Energy Technology Data Exchange (ETDEWEB)

Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

2013-07-01

The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

Radioactive waste management

International Nuclear Information System (INIS)

2003-01-01

Almost all IAEA Member States use radioactive sources in medicine, industry, agriculture and scientific research, and countries remain responsible for the safe handling and storage of all radioactively contaminated waste that result from such activities. In some cases, waste must be specially treated or conditioned before storage and/or disposal. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Energy Department aimed at establishing appropriate technologies and procedures for managing radioactive wastes. (IAEA)

Nuclear-waste management semiannual progress report, April 1982-September 1982

International Nuclear Information System (INIS)

Chikalla, T.D.; Powell, J.A.

1982-12-01

This document is one of a series of technical progress reports designed to report on radioactive waste management programs at Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste treatment; nuclear waste Materials Characterization Center (MCC); airborne waste management; low-level waste management; waste isolation; remedial actions; and supporting studies

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-10-01

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

76 FR 17970 - Board Meeting: April 27, 2011-Amherst, New York; the U.S. Nuclear Waste Technical Review Board...

Science.gov (United States)

2011-03-31

... the 2008-9 study on Quantitative Risk Assessment of the State Licensed Radioactive Waste Disposal Area... of vitrified high-level radioactive waste (HLW); determination of waste classification of the melter... NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting: April 27, 2011--Amherst, New York; the U.S...

Nuclear-waste-management technical support in the development of nuclear-waste-form criteria for the NRC. Task 2. Alternative TRU technologies

International Nuclear Information System (INIS)

Bida, G.; MacKenzie, D.R.

1982-02-01

Three main areas of transuranic (TRU) waste management are addressed: immobilization processes and waste forms for ultimate geologic disposal of TRU waste; decontamination as a method for TRU waste management; and potential problems associated with gas generation by certain TRU wastes. Waste forms are considered in terms of the regulations and criteria proposed in 10 CFR 60. Evaluation of the waste forms is based principally on ability to meet the release rate criterion of 10 -5 /year given in the Performance Objectives of Section 111, but also on the general requirements of Section 133. The two classes of metallic waste which are candidates for decontamination treatment are Zircaloy cladding hulls from light water reactor fuel elements, and failed facilities and equipment. Decontamination methods are addressed with regard to their ability to remove contamination to a level below the 10 nCi/g TRU limit. Other important factors are the volume reduction achieved, and compatibility of the secondary waste streams with acceptable waste forms. Gas generation by combustible TRU wastes and cast concretes containing TRU isotopes is discussed, and its potential for damage to a geologic repository is considered. Exclusion of combustible TRU waste from repositories is recommended. Conclusions are drawn about the suitability of various waste forms and recommendations are made regarding further work needed in the development of specific TRU waste forms

Construction demolition wastes, Waelz slag and MSWI bottom ash: a comparative technical analysis as material for road construction.

Science.gov (United States)

Vegas, I; Ibañez, J A; San José, J T; Urzelai, A

2008-01-01

The objective of the study is to analyze the technical suitability of using secondary materials from three waste flows (construction and demolition waste (CDW), Waelz slag and municipal solid waste incineration (MSWI) bottom ash), under the regulations and standards governing the use of materials for road construction. A detailed technical characterization of the materials was carried out according to Spanish General Technical Specifications for Road Construction (PG3). The results show that Waelz slag can be adequate for using in granular structural layers, while CDW fits better as granular material in roadbeds. Likewise, fresh MSWI bottom ash can be used as roadbed material as long as it does not contain a high concentration of soluble salts. This paper also discusses the adequacy of using certain traditional test methods for natural soils when characterizing secondary materials for use as aggregates in road construction.

Technical report on natural evaporation system for radioactive liquid waste treatment arising from TRIGA research reactors' decontamination and decommissioning activities

International Nuclear Information System (INIS)

Moon, J. S.; Jung, K. J.; Baek, S. T.; Jung, U. S.; Park, S. K.; Jung, K. H.

1999-01-01

This technical report described that radioactive liquid waste treatment for dismantling/decontamination of TRIGA Mark research reactor in Seoul. That is, we try safety treatment of operation radioactive liquid waste during of operating TRIGA Mark research reactor and dismantling radioactive liquid waste during R and D of research reactor hereafter, and by utilizing of new natural evaporation facility with describing design criteria of new natural evaporation facility. Therefore, this technical report described the quantity of present radioactive liquid waste and dismantling radioactive liquid waste hereafter, analysis the status of radial-rays/radioactivity, and also treatment method of this radioactive liquid waste. Also, we derived the method that the safeguard of outskirts environment and the cost down of radioactive liquid waste treatment by minimize of the radioactive liquid waste quantities, through-out design/operation of new natural evaporation facility for treatment of operation radioactive liquid waste and dismantling radioactive liquid waste. (author). 6 refs., 12 tabs., 5 figs

What to do with nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Duncan, I.J

2003-06-01

Technical progress is being made for the geological disposal of radioactive waste but still the concept does not have strong public support. Part of the underlying cause of this resistance is the technical complexity of containment of radiation, geological space and time and mathematical expressions of degrees of hazard and risk. There are additional community concerns, typified by the inherent limitation to forward time projection, and industry must apply more sociology so as to understand better the base to these. There is underlying public support for the proper disposal of all hazardous waste but the schemes must conform to public requirements. A disposal regime that can be reversed, or where the wastes can be recovered if necessary, probably has a higher public acceptance but this needs to be tested. The next advancement in solving the waste issue will come from a better understanding of the public psyche by industry and not by a better understanding of the industry by the public. (author)

Technical support organization of national regulators: Challenges and strategy

International Nuclear Information System (INIS)

Mallick, S.A.; Maqbul, N.; Kanwal, S.; Hashmi, J.A.

2007-01-01

Design, construction and operation of nuclear power plants has always been a complex activity and so is regulating the nuclear power plants. The rapid innovation in design of nuclear power plants with substantial increase in design life from 40 years to 60 years is now considered a norm. The public acceptability of nuclear as a clean source of energy is also on the increase but with this increase is also the demand for more safety against accidental release of radioactivity. It is therefore essential that high standards of nuclear and radiation safety should be maintained and applied all over the world. However the increase acceptability will also lead to a rapid growth in nuclear energy generation capacity both in terms of construction of new nuclear power plants as well as life extension of older nuclear power plants. This will result in an unprecedented pressure on the national regulators during the licensing process. Nuclear and radiation safety are based on technical, administrative and organizational provisions. There is, therefore, a need to separate the technical review and assessment work from the main licensing process by delegating this responsibility to the technical support organizations so that regulatory decision making is not driven by the time constraints imposed by the licensing process. The paper examines the role technical support organization can play to enhance quality of technical review and thereby the effectiveness of national regulators. For the national regulators that belong to countries that import nuclear power plants and may lack an advanced industrial infrastructure at par with other exporting countries, the establishment of technical support organization within a regulatory body or as a separate organization is gaining increased importance. Pakistan Nuclear Regulatory Authority (PNRA) has realized this importance and proposed the Government of Pakistan for allocation of Rs. 480.00 million ($ 8 million) for the establishment of

Nuclear waste management. Semiannual progress report, October 1982-March 1983

International Nuclear Information System (INIS)

Chikalla, T.D.; Powell, J.A.

1983-06-01

This document is one of a series of technical progress reports designed to report radioactive waste management programs at the Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste stabilization; Materials Characterization Center; waste isolation; low-level waste management; remedial action; and supporting studies

Technical development for geological disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Asano, Hidekazu; Sugino, Hiroyuki; Kawakami, Susumu; Yamanaka, Yumiko

1997-01-01

Technical developments for geological disposal of high-level radioactive wastes materials research and design technique for engineered barriers (overpack and buffer material) were studied to evaluate more reliable disposal systems for high-level radioactive wastes. A lifetime prediction model for the maximum corrosion depth of carbon steel was developed. A preferable alloys evaluation method for crevice corrosion was established for titanium. Swelling pressure and water permeability of bentonite as a buffer material was measured, and coupled hydro-thermo-mechanical analysis code for bentonite was also studied. The CIP (cold isostatic pressing) method for monolithically formed buffer material was tested. A concept study on operation equipment for the disposal site was performed. Activities of microorganisms involved in underground performance were investigated. (author)

Technical bases for OCRWM's [Office of Civilian Radioactive Waste Management] policy decisions on international safeguards

International Nuclear Information System (INIS)

Sprecher, W.M.

1989-01-01

The purpose of this paper is to discuss the technical factors that contributed to the formulation of the international safeguards policy enunciated in September 1988 by the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM), which is the federal organization responsible for the implementation of the Nuclear Waste Policy Act of 1982, as amended

Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

International Nuclear Information System (INIS)

Monts, D.L.; Jang, P.R.; Long, Z.; Norton, O.P.; Okhuysen, W.P.; Su, Y.; Waggoner, Ch.A.

2009-01-01

The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)

Michigan high-level radioactive waste program. Technical progress report for 1985

International Nuclear Information System (INIS)

1986-01-01

In 1985, five crystalline rock formations located in Michigan's Upper Peninsula were under consideration in the regional phase of the Department of Energy's (DOE) search for the site of the nation's second high-level radioactive waste repository. The Michigan Department of Public Health has been designated by the Governor as lead state agency in matters related to high-level radioactive waste (HLRW). Mr. Lee E. Jager, Chief of the Department's Bureau of Environmental and Occupational Health, has been designated as the state contact person in this matter, and the Bureau's Division of Radiological Health, Office of Radioactive Waste Management (ORWM), has been designated to provide staff support. Recognizing that adequate state involvement in the various aspects of the Federal high-level radioactive waste (HLRW) programs would require a range of expertise beyond the scope of any single state agency, Governor Blanchard established the High-Level Radioactive Waste Task Force in 1983. In support of the Task Force efforts concerning the implementation of its change, the Department negotiated and concluded an agreement with the DOE, under which federal funds are provided to support state HLRW activities. This report outlines state activities for the calendar year 1985, funded under that agreement

Educational support programs: Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Williamson, R.C.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two educationally related programs: the Radioactive Waste Management Fellowship Program and the Radioactive Waste Management Research Program for Historically Black Colleges and Universities (HBCU). The graduate fellowship program was implemented in 1985 to meet the US Department of Energy's (DOE's) expected manpower needs for trained scientists and engineers to assist in carrying out the activities of the Nuclear Waste Policy Act. It is recognized that a shortage of master's and doctoral level scientists and engineers in disciplines supportive of the nation's high-level radioactive waste management (RWM) program may impede the DOE's ability to properly carry out its mission under the act. The fellowship program encourages talented undergraduate students to enter graduate programs designed to educate and train them in fields directly related to RWM. The program supports graduate students in various disciplines, including nuclear science and engineering, health physics, and certain area of geology and chemical engineering. It also encourages universities to support and improve research activities and academic programs related to the management of spent nuclear fuel and high-level radioactive waste

Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

International Nuclear Information System (INIS)

Galkin, A.V.; Baldov, A.N.

2001-01-01

In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

Dismantling of civilian nuclear powered fleet technical support vessels. engineering solutions - 59386

International Nuclear Information System (INIS)

Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

2012-01-01

At the present time six nuclear technical support vessels are operated and maintained by Atomflot. Two of them (Volodarsky FTB (floating technical base) and Lepse FTB) were taken out of service for decommissioning and are stored afloat. One more vessel Lotta FTB should be decommissioned during next two years. The nuclear technological support ships carrying spent nuclear fuel (SNF), liquid and solid radioactive wastes (LRW and SRW) appear to be a possible radiation contamination of Murmansk region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull's structures technical condition. As a result of this in the context of the Federal Program 'Nuclear and Radiation Safety' (2008-2015) NIPTB Onega OAO was engaged by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB. Before developing of nuclear technological support ships decommissioning projects the technical and economic assessment of decommissioning/dismantling was carried out. The following options were examined: - formation of module as one-piece Ship's hull for long-term storage at Saida Bay; - formation of separated modules for long-term storage at Saida Bay; - complete dismantling of hull's structures, systems and equipment with packing all generated SRW into certified long-term storage containers. This paper contains description of options, research procedure, comparative analysis of options of decommissioning and dismantling (D and D) of nuclear technological support ships and its difference with dismantling of nuclear submarine. On the basis of the technical and economic assessment of FTB D and D options the least expensive on the first D and D stage and the least duration option is the option 1 (Formation of module as one-piece Ship's hull for long-term storage at Saida Bay). By the implementation of the given option there will be the need of large areas for modules storage at Saida Bay. It was not considered while working out

Licensing of alternative methods of disposal of low-level radioactive waste: Branch technical position, Low-Level Waste Licensing Branch

International Nuclear Information System (INIS)

Higginbotham, L.B.; Dragonette, K.S.; Pittiglio, C.L. Jr.

1986-12-01

This branch technical position statement identifies and describes specific methods of disposal currently being considered as alternatives to shallow land burial, provides general guidance on these methods of disposal, and recommends procedures that will improve and simplify the licensing process. The statement provides answers to certain questions that have arisen regarding the applicability of 10 CFR 61 to near-surface disposal of waste, using methods that incorporate engineered barriers or structures, and other alternatives to conventional shallow land burial disposal practices. This position also identifies a recently published NRC contractor report that addresses the applicability of 10 CFR 61 to a range of generic disposal concepts and which provides technical guidance that the staff intends to use for these concepts. This position statement combined with the above-mentioned NRC contractor report fulfills the requirements of Section 8(a) of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985

Characterization of radioactive waste forms and packages

International Nuclear Information System (INIS)

1997-01-01

This publication provides a compendium of waste form, container and waste package properties which are potential importance for waste characterization to support approval for treatment/conditioning, storage and disposal methods and for predicting both short and long term waste behaviour in the repository environment. The properties to be characterized are defined in terms of the technical rationale for their control and characterization. Characterization methods for each property are described in general with reference to detailed discussions existing in the literature. Guidance as to the advantages and disadvantages of individual methods from a technical perspective is also provided where appropriate. This report deals with the characterization of all types of radioactive wastes except spent fuel intended for direct disposal. 115 refs, 17 figs, 12 tabs

International technology exchange in support of the Defense Waste Processing Facility wasteform production

International Nuclear Information System (INIS)

Kitchen, B.G.

1989-01-01

The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

Optimised anaerobic treatment of house-sorted biodegradable waste and slaughterhouse waste in a high loaded half technical scale digester.

Science.gov (United States)

Resch, C; Grasmug, M; Smeets, W; Braun, R; Kirchmayr, R

2006-01-01

Anaerobic co-digestion of organic wastes from households, slaughterhouses and meat processing industries was optimised in a half technical scale plant. The plant was operated for 130 days using two different substrates under organic loading rates of 10 and 12 kgCOD.m(-3).d(-1). Since the substrates were rich in fat and protein components (TKN: 12 g.kg(-1) the treatment was challenging. The process was monitored on-line and in the laboratory. It was demonstrated that an intensive and stable co-digestion of partly hydrolysed organic waste and protein rich slaughterhouse waste can be achieved in the balance of inconsistent pH and buffering NH4-N. In the first experimental period the reduction of the substrate COD was almost complete in an overall stable process (COD reduction >82%). In the second period methane productivity increased, but certain intermediate products accumulated constantly. Process design options for a second digestion phase for advanced degradation were investigated. Potential causes for slow and reduced propionic and valeric acid degradation were assessed. Recommendations for full-scale process implementation can be made from the experimental results reported. The highly loaded and stable codigestion of these substrates may be a good technical and economic treatment alternative.

Cooperation of Russian and EU technical support organizations

International Nuclear Information System (INIS)

Kuznetsov, M.V.; Kozlov, Vl.V.; Kapralov, E.Yu.

2007-01-01

Since 1992, the fruitful collaboration of the Russian and Western-European technical support organizations (TSOs) is being continued due to the support of the European Commission. There are two main areas of activities. The first one is more of methodological assistance and enhancing RF TSOs capabilities to support Rostekhnadzor decision making process. Experience and knowledge acquired in this area projects increase RF TSOs capabilities regarding a wide spectrum of safety related issues assessment, in particular safety analyses, reactor vessel embrittlement, application of 'leak before break' concept, severe accident and accident management, fire risk evaluation, etc. The second area is focused on licensing related assessments of EC financed on site assistance projects (modernisations). This area projects promote implementation in Russia a licensing process based on a technical dialogue between operator and regulator as well contributes to transfer of Western practice in assessment of NPPs modernization. The improvement of managerial, scientific and technical capabilities of RF TSO experts may be considered as noteworthy and practical result of the TSOs cooperation. The continuation of such modality of RF and EU TSOs cooperation will be a good basis to cope with present and future challenges faced by TSOs in enhancing nuclear safety. (author)

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C. Jr.; Cashwell, J.W.; Jefferson, R.M.

1983-01-01

Transportation Technology Center has been conducting a wide range of technical research activities to assure the ability to transport radioactive materials in a safe, reliable manner. These activities include tasks in basic, analysis methodology and system research areas. Recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on the Department of Energy for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Review on technical issues influencing the performance of chemical barriers of TRU waste repository

International Nuclear Information System (INIS)

Fujita, Tomonari; Sugiyama, Daisuke; Tsukamoto, Masaki; Yokoyama, Hayaichi

1997-01-01

Studies of technical issues influencing the performance assessment of TRU waste disposal which is occurred from the nuclear fuel reprocessing were reviewed in related to the development of safety analysis method. Especially, the chemical containment was investigated as a key barrier to radionuclide migration. TRU waste including long-lived radionuclides need long-term performance assessment which could be assumed only by the chemical barrier. The description of technical issues concerned with the performance of TRU waste repository has been divided into the following categories: long-term degradation of cementitious materials as engineered barrier for radionuclide migration, effect of colloids, organic macromolecules and organic degradation products on chemical behavior of radionuclides, gas generation by corrosion of metallic wastes, and effects of microbial activity. Preliminary performance assessment indicated that important factors affecting performance of chemical barriers in near-field were the distribution coefficient and the solubility of radionuclides in near-field groundwater. Therefore, it was identified that key issues associated with performance of chemical barrier were evaluation of (a) the long-term change of distribution coefficient of cementitious material through the degradation under repository condition and (b) chemical speciation change of radionuclides such as increase of solubility by the presence of colloidal-size materials. (author)

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

International Nuclear Information System (INIS)

Anon.

1988-01-01

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

Hospital waste sterilization: a technical and economic comparison between radiation and microwave treatments

International Nuclear Information System (INIS)

Tata, A.; Beone, F.

1995-01-01

Hospital waste (HW) disposal is becoming a problem of increasing importance in almost all industrially advanced countries. In Italy the yearly hospital waste production is about 250,000 tons and only 60,000 are treated by incineration at present time. As by a recent Italian law a meaningful percentage of HW (50 to 60%), corresponding to food residuals, plastic, paper, various organic materials, etc., could be landfilled as municipal refuses if preliminarily submitted to a suitable sterilization treatment. Under this perspective, sterilization/sanitation techniques represent now a technically and commercially viable alternative to HW thermal destruction that, besides more and more socially and politically less accepted. Electron Beam (EB) and Microwave (MW) treatments are two of the most interesting and emerging HW sterilization techniques, and, based on engineering real data, a technical and economic comparison is carried out, focusing vantages and limits of each process. (author)

Draft Technical Position Subtask 1.1: waste package performance after repository closure. Volume 1

International Nuclear Information System (INIS)

Davis, M.S.; Schweitzer, D.G.

1983-08-01

This document provides guidance to the DOE on the issues and information necessary for the NRC to evaluate waste package performance after repository closure. Minimal performance objectives of the waste package are required by proposed 10 CFR 60. This Draft Technical Position describes the various options available to the DOE for compliance and discusses advantages and disadvantages of various choices. Examples are discussed dealing with demonstrability, predictability and reasonable assurance. The types of performance are considered. The document summarizes presently identified high priority issues needed to evaluate waste package performance after repository closure. 20 references, 7 tables

Technical guidelines for environmental dredging of contaminated sediments

Science.gov (United States)

2008-09-01

This report provides technical guidelines for evaluating : environmental dredging as a sediment remedy component. This document : supports the Contaminated Sediment Remediation Guidance for : Hazardous Waste Sites, released by the U.S. Environmental ...

Low level waste management at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rodgers, A.D.; Truitt, D.J.; Logan, J.A.; Brown, R.M.

1986-02-01

EG and G Idaho, Inc. is the lead contractor for the Department of Energy (DOE) National Low Level Waste Management Program, established in 1979. In this role, the company uses its waste management expertise to provide management and technical direction to support the disposal of low-level waste (LLW) in a manner that protects the environment and the public health and safety while improving efficiency and cost-effectiveness. Program activities are divided into two areas: defense-related and commercial nuclear reactor programs. The defense program was established to develop technology improvements, provide technology transfer, and to ensure a more efficient and uniform system for low level waste disposal. To achieve the program's goals, it is necessary to improve, document, and, where necessary, develop new methods for waste generation reduction, waste treatment, shallow-land burial, greater confinement disposal, and measures to correct existing site deficiencies. The commercial low level waste management program provides support to assist the states in developing an effective national low level waste management system and provides technical assistance for siting of regional commercial LLW disposal sites. The program provides technical and informational support to state officials, low level waste generators, managers, and facility operators to resolve low level waste problems and to improve the systems' overall effectiveness. Procedures are developed and documented and made available to commercial users through this program. Additional work is being conducted to demonstrate the stabilization and closure of low level radioactive waste disposal sites and develop the criteria and procedures for acceptance of such sites by the Department of Energy after closure has been completed. 7 refs., 6 figs., 1 tab

Technical development of graphite waste treatment in NUPEC

International Nuclear Information System (INIS)

Saishu, S.; Inoue, T.

2001-01-01

In Japan, Tokai Power Station, which is a Gas Cooled Reactor and uses graphite as moderator, ceased operation at the end of March in 1998 and it is planned to transfer to decommissioning stage. In this decommissioning stage it is very important to be able to treat and dispose the graphite waste in order to carry out the decommissioning safely and economically. NUPEC has been developing the graphite treatment and disposal technology since 1997 and we introduce the outline of the technical development. For the technology on high density packing into disposal container, the high density packing method and the assessment method on nuclide leaching characteristics were developed, and the cementing test for graphite powder by using Tokai spare graphite was performed and the hydrophobic characteristics between graphite and cement was grasped and the accelerator candidature for affinity was selected. From the view point of economical treatment, the incinerating technology was selected as candidature, and the methods for incinerating graphite and treating off gas are developed. The method of collecting C-14 in off gas was selected for reducing the off gas radiation level. The applicability of actual graphite treatment technology was considered from the view point of safety, economics and preparation of technical standard; the technical theme appeared, the developing planning items were established, and the detailed and actual scale tests will be carried out according to the planning. (author)

SRS Public Involvement in Waste Management Has Resulted in Effective Decisions Supported by the Public Including Disposal Changes and Top-to-Bottom Review Initiative Consensus

International Nuclear Information System (INIS)

Goldston, W. T.; Villasor, H. P.

2003-01-01

In the Savannah River Site's (SRS') Solid Waste Management Program, a key to success is the Public Involvement Program. The Solid Waste Division at SRS manages the site's transuranic, low-level, mixed, and hazardous wastes. All decisions associated with management of this waste are of interest to the public and successful program implementation would be impossible without a vigorous public involvement program. The SRS Solid Waste Division (SWD) and its Department of Energy (DOE) customer developed, implemented, and maintain a comprehensive public participation and communications program. It is staffed by public participation and technical specialists to ensure information is presented in a manner that is technically accurate while being tailored for understanding by people without a technical background. The program provides the public with accurate, complete, timely information and early meaningful participation opportunities. It also fulfills the public participation activities required by laws, regulations, DOE Orders, and negotiated agreements. The primary goal of the SWD Public Participation Program is to fulfill the objectives of the SWD and SRS Strategic Plans to ''build trust and communicate openly, honestly, and responsibly with employees, customers, stakeholders, and regulators,'' and to ''work to extend the support of external stakeholders for the pursuit of SRS and DOE Complex business goals.'' This paper focuses on the public participation program goals, the implementation through formal plans and objectives, targeted waste management programs and specific audiences, and specific effects of the program on waste management activities. A discussion of the DOE and contractor teaming along with how plans are carried out is also included

PACCOM: A nuclear waste packaging facility cost model: Draft technical report

International Nuclear Information System (INIS)

Dippold, D.G.; Tzemos, S.; Smith, D.J.

1985-05-01

PACCOM is a computerized, parametric model used to estimate the capital, operating, and decommissioning costs of a variety of nuclear waste packaging facility configurations. The model is based upon a modular waste packaging facility concept from which functional components of the overall facility have been identified and their design and costs related to various parameters such as waste type, waste throughput, and the number of operational shifts employed. The model may be used to either estimate the cost of a particular waste packaging facility configuration or to explore the cost tradeoff between plant capital and labor. That is, one may use the model to search for the particular facility sizes and associated cost which when coupled with a particular number of shifts, and thus staffing level, leads to the lowest overall total cost. The functional components which the model considers include hot cells and their supporting facilities, transportation, cask handling facilities, transuranic waste handling facilities, and administrative facilities such as warehouses, security buildings, maintenance buildings, etc. The cost of each of these functional components is related either directly or indirectly to the various independent design parameters. Staffing by shift is reported into direct and indirect support labor. These staffing levels are in turn related to the waste type, waste throughput, etc. 2 refs., 11 figs., 3 tabs

Methods for communicating technical information as public information

International Nuclear Information System (INIS)

Zara, S.A.

1987-01-01

Many challenges face the nuclear industry, especially in the waste management area. One of the biggest challenges is effective communication with the general public. Technical complexity, combined with the public's lack of knowledge and negative emotional response, complicate clear communication of radioactive waste management issues. The purpose of this session is to present and discuss methods for overcoming these obstacles and effectively transmitting technical information as public information. The methods presented encompass audio, visual, and print approaches to message transmission. To support these methods, the author also discusses techniques, based on current research, for improving the communication process

The Challenge of Development of a Holistic Waste Management Approach to Support the Nuclear Renaissance

International Nuclear Information System (INIS)

Makino, H.; Umeki, H.; Hioki, K.; McKinley, I.G.

2009-01-01

The recent growth of interest in atomic power, the 'nuclear renaissance', is undoubtedly driven by environmental concerns. Nevertheless, there are many opponents to such a move and, increasingly, their arguments focus on the back-end of the nuclear cycle, with waste disposal claimed to be the 'Achilles Heel' of nuclear power. It is clear that nuclear expansion - and introduction of advanced fuel cycles - will face intense scrutiny and a clear case must be made for its advantages, which will require an improved, integrated approach to waste management. Unlike the present, dispersed system that focuses only on disposal of individual waste streams, a holistic waste management approach needs to be developed for the entire back-end. In this paper, the technical challenges associated with the development of such a holistic waste management approach will be discussed in the context of recent progress in relevant technical areas, especially introduction of optimized approaches for repository design and safety assessment. (authors)

Technical Support Document for Version 3.6.1 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2009-09-29

This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards.

Technical, institutional and economic factors important for developing a multinational radioactive waste repository

International Nuclear Information System (INIS)

1998-06-01

Countries planning and implementing nuclear energy programmes should assume responsibility for the safe management and final disposal of radioactive waste from their programmes. However, there are countries whose radioactive waste volumes do not easily justify a national repository, and/or countries which do not have the resources or favorable natural conditions for waste disposal to dedicate to a national repository project. These countries would benefit from multinational co-operation for the disposal. Interest in the concept of a multinational repository for radioactive waste has been expressed by several Member States and the waste management community in the light of the potential benefit to the partner countries from the safety, technical and economic standpoints. However, such an approach involves many political and public acceptance issues and therefore a consensus among countries or regions concerned is a prerequisite. In this context, it was deemed appropriate that the IAEA access the technical, institutional, ethical and economic factors to be taken into account in the process of such consensus building. This report is intended to provide an assessment which can serve as a general basis for establishing a waste management policy and/or further assessing specific issues such as ownership and liability, institutional aspects and problems related to long term commitments. This report is divided into five sections where the first section gives background, objectives, scope and structure of the report. Section 2 discusses multinational repository concept in terms of needs and the role of a multinational repository, interaction between host and partner countries and formulation of a multinational repository. Section 3 identifies basic issues to be considered for establishing a multinational repository, and some specific issues relating to specific waste categories. Section 4 analyses potential benefits and challenges to be addresses in establishing a

Methodology for the technical evaluation of disposal systems for Greater-Than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Lamar, D.A.; Raymond, J.R.

1990-07-01

This paper presents the methodology that will be used for the evaluation of alternative disposal concepts for Greater-Than-Class C low-level radioactive waste. The primary focus will be on the technical evaluation of various disposal concepts leading toward the identification of technically feasible disposal systems

DOE Waste Treatability Group Guidance

International Nuclear Information System (INIS)

Kirkpatrick, T.D.

1995-01-01

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

DOE Waste Treatability Group Guidance

Energy Technology Data Exchange (ETDEWEB)

Kirkpatrick, T.D.

1995-01-01

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

Radioactive waste disposal programme 2008 of the waste-management-compelled bodies. Technical report 08-01

International Nuclear Information System (INIS)

2008-10-01

Important steps in the management of radioactive waste have already been implemented in Switzerland and there is now wide experience in carrying out the associated activities. In terms of preparing for deep geological disposal, the necessary scientific and technical work is well advanced and the feasibility of implementing geological repositories that provide the required long-term safety has been successfully demonstrated for all wastes arising in Switzerland. Test feasibility demonstrations have also been approved by the Federal Council. Sufficient knowledge is available to allow the next steps in the selection of repository sites to be performed. The legal framework and organisational measures are also in place. The conceptual part of the Sectoral Plan for deep geological repositories regulates the details of the site selection process to be conducted over the next years. The origin, types and volumes of radioactive waste to be disposed of in Switzerland are known. The reference case assumes operation of the existing nuclear power plants for a period of 50 years and a collection period up to around 2050 for radioactive waste from medicine, industry and research. The types and volumes of radioactive waste that would arise in the case of extension of the operating lifetime of the existing power plants and the collection period for waste from medicine, industry and research by 10 years are included for planning purposes. Also considered are the wastes to be expected in the case of an additional production of 5 GW e for a period of 60 years. The resulting wastes are conditioned, characterised and inventoried on an ongoing basis. Before conditioning of a waste stream begins, the proposed conditioning procedure is evaluated by Nagra in terms of the suitability for disposal of the resulting waste packages. A model inventory of waste that will arise in the future has also been compiled. This provides a reliable basis for planning and implementing geological repositories

Managing mixed wastes: technical issues

International Nuclear Information System (INIS)

Lytle, J.E.; Eyman, L.D.; Burton, D.W.; McBrayer, J.F.

1986-01-01

The US Department of Energy manages wastes that are both chemically hazardous and radioactive. These mixed wastes are often unique and many have national security implications. Management practices have evolved over the more than forty years that the Department and its predecessor agencies have been managing these wastes, both in response to better understanding of the hazards involved and in response to external, regulatory influences. The Department has recently standarized its waste management practices and has initited an R and D program to address priority issues identified by its operating contractor organizations. The R and D program is guided by waste management strategy that emphasizes reduction of human exposure to hazardous wastes in the environment, reduction of the amount and toxicity of wastes generated, treatment of wastes that are generated to reduce volumes and toxicities, and identification of alternatives to land disposal of wastes that remain hazardous following maximum practicable treatment

Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, fiscal year 1987

International Nuclear Information System (INIS)

1988-01-01

This multidisciplinary project was initiated in fiscal year 1986. It comprises 11 reports in two major interrelated tasks: The technical assistance part of the project includes reviewing the progress of the major projects in the DOE Office of Civilian Radioactive waste Management (OCRWM) Program and advising the Engineering and Geotechnology Division on significant technical issues facing each project; analyzing geotechnical data, reports, tests, surveys and plans for the different projects; reviewing and commenting on major technical reports and other program documents such as Site Characterization Plans (SCP) and Study Plans; and providing scientific and technical input at technical meetings. The topical studies activity comprises studies on scientific and technical ions and issues of significance to in-situ testing, test analysis methods, and site characterization of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. One minor topic is a preliminary consideration and planning exercise for postclosure monitoring studies. The major task, with subtasks involving various geoscience disciplines, is a study of the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses

Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL

International Nuclear Information System (INIS)

1993-10-01

The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical waste to LBL's Hazardous Waste Handling Facility (HWHF). Hazardous chemical waste is a necessary byproduct of LBL's research and technical support activities. This waste must be handled properly if LBL is to operate safely and provide adequate protection to staff and the environment. These guidelines describe how you, as a generator of hazardous chemical waste, can meet LBL's acceptance criteria for hazardous chemical waste

Updated Liquid Secondary Waste Grout Formulation and Preliminary Waste Form Qualification

Energy Technology Data Exchange (ETDEWEB)

Saslow, Sarah A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russell, Renee L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Asmussen, Robert M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sahajpal, Rahul [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-07-01

This report describes the results from liquid secondary waste grout (LSWG) formulation and cementitious waste form qualification tests performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). New formulations for preparing a cementitious waste form from a high-sulfate liquid secondary waste stream simulant, developed for Effluent Management Facility (EMF) process condensates merged with low activity waste (LAW) caustic scrubber, and the release of key constituents (e.g. ⁹⁹Tc and ¹²⁹I) from these monoliths were evaluated. This work supports a technology development program to address the technology needs for Hanford Site Effluent Treatment Facility (ETF) liquid secondary waste (LSW) solidification and supports future Direct Feed Low-Activity Waste (DFLAW) operations. High-priority activities included simulant development, LSWG formulation, and waste form qualification. The work contained within this report relates to waste form development and testing and does not directly support the 2017 integrated disposal facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY17, and for future waste form development efforts. The provided data should be used by (i) cementitious waste form scientists to further understanding of cementitious dissolution behavior, (ii) IDF PA modelers who use quantified constituent leachability, effective diffusivity, and partitioning coefficients to advance PA modeling efforts, and (iii) the U.S. Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program. The results obtained help fill existing data gaps, support final selection of a LSWG waste form, and improve the technical defensibility of long-term waste form performance estimates.

Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

International Nuclear Information System (INIS)

Ulm, Franz-Josef

2000-01-01

OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

Waste compatibility assessments to support project W-320

International Nuclear Information System (INIS)

BLAAK, T.M.

1999-01-01

The intent of this internal memo is to provide a recommendation for the transfer of tank 241-C-106 waste, Attachment 2, to tank 241-AY-102. This internal memo also identifies additional requirements which have been deemed necessary for safely receiving and storing the waste documented in Attachment 2 from tank 241-C-106 in tank 241-AY-102. This waste transfer is planned in support of tank 241-C-106 solids sluicing activities. Approximately 200,000 gallons of waste and flush water are expected to be pumped from tank 241-C-106 into tank 241-AY-102. Several transfers will be necessary to complete the sluicing of tank 241-C-106 solids. To assure ourselves that this waste transfer will not create any compatibility concerns, a waste compatibility assessment adhering to current waste compatibility requirements has been performed

Data base for radioactive waste management: review of low-level radioactive waste disposal history

International Nuclear Information System (INIS)

Clancy, J.J.; Gray, D.F.; Oztunali, O.I.

1981-11-01

This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 1 is a summary and analysis of the history of low level waste disposal at both commercial and government disposal facilities

TWRS technical baseline database manager definition document

International Nuclear Information System (INIS)

Acree, C.D.

1997-01-01

This document serves as a guide for using the TWRS Technical Baseline Database Management Systems Engineering (SE) support tool in performing SE activities for the Tank Waste Remediation System (TWRS). This document will provide a consistent interpretation of the relationships between the TWRS Technical Baseline Database Management software and the present TWRS SE practices. The Database Manager currently utilized is the RDD-1000 System manufactured by the Ascent Logic Corporation. In other documents, the term RDD-1000 may be used interchangeably with TWRS Technical Baseline Database Manager

Igneous Intrusion Impacts on Waste Packages and Waste Forms

International Nuclear Information System (INIS)

P. Bernot

2004-01-01

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and

Igneous Intrusion Impacts on Waste Packages and Waste Forms

Energy Technology Data Exchange (ETDEWEB)

P. Bernot

2004-08-16

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and

TECHNICAL SUPPORT AS A BASIS OF HIGH AVAILABILITY LEVEL AND IT SYSTEM SERVICE QUALITY

Directory of Open Access Journals (Sweden)

Dejan Vidojevic

2007-06-01

Full Text Available This work presents the development and implementation methodology of technical support in IT1system operation. Methodology is developed and applied in realistic system (Information system of the Tax administration - DIS 2003, which is technically very complex and highly distributed. The results of IT system availability assessment and identification of the critical components are input parameters in the process of establishing of the technical support. The importance of technical support for achieving optimal IT system availability and IT service quality is assessed according to its operation during one year. The history of technical support system operation is a basis for further continuous improvement.

Technical support for nuclear power operations

International Nuclear Information System (INIS)

1999-04-01

This report prepared by the group of senior experts from nuclear operating organizations in Member states, addresses the problem of improving the operating performance of nuclear power plants. Safe and reliable operation is essential for strengthening the viability of nuclear power in the increasingly competitive market of electric power. Basic principles and requirements concerning technical procedures and developed practices are discussed. Report reflects the best current international practices and presents those management initiatives that go beyond the mandated regulatory compliance and could lead to enhancement od operational safety and improved plant performance. By correlating experiences and presenting collective effective practices it is meant to assist nuclear power plant managers in achieving improvement in operation through the contribution of effective technical support

Greater-than-Class C low-level waste characterization technical review process

Energy Technology Data Exchange (ETDEWEB)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs.

Greater-than-Class C low-level waste characterization technical review process

International Nuclear Information System (INIS)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs

A preliminary redrafting of the Italian technical guide no.26 on radioactive waste management

International Nuclear Information System (INIS)

Tocci, M.

1993-01-01

The recent National Energy Plan confirms the need for reprocessing of the nuclear spent fuel arising from the Nuclear Power Plants (NPPs) that were definitively put out of operation after Chernobyl accident. Two campaigns concerning the Italian spent fuel reprocessing are starting at this time. The first-one is related to LATINA (MAGNOX, GCR 160 MWe) while the second one will concern GARIGLIANO (BWR 160 MWe), CAORSO (BWR 840 MWe) and TRINO (PWR, 200 MWe). The first campaign will involve about 600 tons of MAGNOX spent fuel arising from LATINA NPP which will be reprocessed in the next future by BNFL (British Nuclear Fuel Limited) at Sellafield. The vitrified High Level Wastes (HLW) shall return to Italy starting from 1994. ENEA-DISP (Italian directorate for Nuclear Safety) has received from BNFL the technical specifications of the glass blocks. The approval of those specifications is scheduled by the end of 1993, in order to allow the delivery of the wastes. During the licensing iter ENEA-DISP will use its own Technical Guide N. 26, which identifies and specifies the basic criteria and requirements for an appropriate waste management policy. (author). 4 figs., 5 refs

Technical data summary supporting the spent nuclear fuel environmental impact statement, November 1993

International Nuclear Information System (INIS)

Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

1993-11-01

This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River site data evaluates five programmatic options including open-quotes No Actionclose quotes ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a 50 period (to 2044) when it is assumed that the material will be dispositioned from the SRS. It must be recognized that this report was prepared under severe time constraints and contains many simplifications and assumptions. It is highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. It represents a best effort by a significant group of technical personnel familiar with nuclear materials processing, handlings and storage but it is likely that careful scrutiny will reveal numerous discrepancies and omissions. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an Environmental Impact Statement, has not been completed at this time

Waste Isolation Pilot Plant supplementary roof support system underground storage area, Panel 1, Room 1

International Nuclear Information System (INIS)

1991-10-01

WIPP is designed to provide a full-scale facility to demonstrate the technical and operational principles for permanent isolation of defense-generated transuranic waste. It is also designed to provide a facility in which studies and experiments can be conducted. Bin Scale Tests are being planned as part of the WIPP Test Phase Performance Assessment Program described in the WIPP Test Phase Plan: Performance Assessment (DOE 1990 b). These Tests are anticipated to be conducted over a period of up to seven years. Room 1 of Panel 1 of the Underground Storage Area is to be used as the location of the Bin-Scale Tests to investigate the generation of gas from the waste that is proposed to be stored at the WIPP in the near future. The original design for the waste storage rooms in Panel 1 provided for a limited period of time during which to mine the openings and to emplace waste. Room 1 was initially mined to rough dimensions in 1986. Information obtained from the Site and Preliminary Design Validation (SPDV) program showed that the rooms would remain stable without ground support and that creep closure would not adversely affect equipment clearances during at least five years following excavation

Technical and economic evaluation of processes being developed for solid waste processing

International Nuclear Information System (INIS)

Tittlova, E.; Hladky, E.

1985-01-01

An analysis was made of the economic benefits of two developed processes for reducing the volume of solid radioactive wastes prior to disposal, namely compacting and incineration. Input data were obtained from the actual production of solid radioactive wastes at the V-1 nuclear power plant, from compacting on site, and the operation of an experimental incineration plant. The two WWER-440 units of the V-1 nuclear power plant generate ca 200 m 3 of wastes per annum (not including air filters and wood) of which 69% is assumed to be incinerable and 27% compactable. The rest is disposed of without prior volume reduction. Disposal costs are assessed at 7,500 Czechoslovak crowns per 1 m 3 of wastes, representing a total of 1.5 million crowns per annum. As compared with the disposal of unprocessed wastes the compacting of 95% of wastes generated, reduces the costs of transport and disposal to 25%. With both compacting and incineration, the costs represent 16 to 25% of the initial sum, depending on the ratio of the two processes. The high capital costs of building the incineration plant will thus be offset by the reduction in costs of the radioactive waste disposal. From the technical point of view the analysis did not make a detailed comparison of the properties of the compacted incinerable wastes and ash with regard to stability and leachability of radionuclides. It did also not take into account operating costs and the technological challenge of the two waste volume redution processes. (Z.M.)

Hazardous Waste Remedial Actions Program: integrating waste management

International Nuclear Information System (INIS)

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

1986-01-01

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

Rock support for nuclear waste repositories

International Nuclear Information System (INIS)

Abramson, L.W.; Schmidt, B.

1984-01-01

The design of rock support for underground nuclear waste repositories requires consideration of special construction and operation requirements, and of the adverse environmental conditions in which some of the support is placed. While repository layouts resemble mines, design, construction and operation are subject to quality assurance and public scrutiny similar to what is experienced for nuclear power plants. Exploration, design, construction and operation go through phases of review and licensing by government agencies as repositories evolve. This paper discusses (1) the various stages of repository development; (2) the environment that supports must be designed for; (3) the environmental effects on support materials; and (4) alternative types of repository rock support

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

Spray Calciner/In-Can Melter high-level waste solidification technical manual

International Nuclear Information System (INIS)

Larson, D.E.

1980-09-01

This technical manual summarizes process and equipment technology developed at Pacific Northwest Laboratory over the last 20 years for vitrification of high-level liquid waste by the Spray Calciner/In-Can Melter process. Pacific Northwest Laboratory experience includes process development and demonstration in laboratory-, pilot-, and full-scale equipment using nonradioactive synthetic wastes. Also, laboratory- and pilot-scale process demonstrations have been conducted using actual high-level radioactive wastes. In the course of process development, more than 26 tonnes of borosilicate glass have been produced in 75 canisters. Four of these canisters contained radioactive waste glass. The associated process and glass chemistry is discussed. Technology areas described include calciner feed treatment and techniques, calcination, vitrification, off-gas treatment, glass containment (the canister), and waste glass chemistry. Areas of optimization and site-specific development that would be needed to adapt this base technology for specific plant application are indicated. A conceptual Spray Calciner/In-Can Melter system design and analyses are provided in the manual to assist prospective users in evaluating the process for plant application, to provide equipment design information, and to supply information for safety analyses and environmental reports. The base (generic) technology for the Spray Calciner/In-Can Melter process has been developed to a point at which it is ready for plant application

Technical Support for the development of DCS

International Nuclear Information System (INIS)

Oh, In Seok; Lee, Cheol Kwon; Kim, Dong Hoon; Kim, Jung Taek; Hwang, In Koo; Park, Jae Chang; Lee, Dong Young; Park, Won Man

2008-05-01

The objective of this project is to provide a technical support to Woori Tech Co. in its design and manufacture process of the DCS as a part of KNICS development program to promote the technology self-reliance for non-safety equipment for NPPs(Nuclear Power Plants). We support Woori Tech Co. to develop a DCS which satisfies the requirements for Shinkori 3 and 4 NPPs in the aspects of reliability, applicability and technical competitiveness. As the results of this project the following items were developed and/or implemented; · Design basis and requirements for a DCS system · Design requirements for control communication networks · Architecture of control networks · Design requirements of EWS(Engineering Workstation) · Plan of software verification and validation · Operation display design · Soft control functions · Application development tools of DCS · Analysis and V/V activities on DCS control network protocols · Software verification and validation and documentation guidelines · User manual documents

Impact of Technical Support on Customer Satisfaction

Directory of Open Access Journals (Sweden)

Natasa Gajic

2015-10-01

Full Text Available Technical support through co-creation of value in automotive paint processes and activities is essential to the success of paint manufacturing companies. This study aimed to explore the impact of technical support on customer satisfaction through value-in-use in the automotive paint market. A quantitative questionnaire survey involving a convenience sample of 169 respondents was used for data collection. The questionnaire design bore on the SERVPERF instrument with embedded value-in-use attributes. The data were analyzed by using SPSS 21 statistical methods exploratory factor analysis (EFA and multiple regression analysis (MRA. The findings of this study revealed that the key value-in-use attributes were relationship quality (trust, knowledge required for providing help in getting maximum product benefits, sharing of knowledge, and a range of product and service offerings that satisfy customer needs. Trust had the greatest impact on customer satisfaction. The results also revealed that service quality dimension assurance exerted the greatest positive impact on customer satisfaction.

Decision support models for solid waste management: Review and game-theoretic approaches

International Nuclear Information System (INIS)

Karmperis, Athanasios C.; Aravossis, Konstantinos; Tatsiopoulos, Ilias P.; Sotirchos, Anastasios

2013-01-01

Highlights: ► The mainly used decision support frameworks for solid waste management are reviewed. ► The LCA, CBA and MCDM models are presented and their strengths, weaknesses, similarities and possible combinations are analyzed. ► The game-theoretic approach in a solid waste management context is presented. ► The waste management bargaining game is introduced as a specific decision support framework. ► Cooperative and non-cooperative game-theoretic approaches to decision support for solid waste management are discussed. - Abstract: This paper surveys decision support models that are commonly used in the solid waste management area. Most models are mainly developed within three decision support frameworks, which are the life-cycle assessment, the cost–benefit analysis and the multi-criteria decision-making. These frameworks are reviewed and their strengths and weaknesses as well as their critical issues are analyzed, while their possible combinations and extensions are also discussed. Furthermore, the paper presents how cooperative and non-cooperative game-theoretic approaches can be used for the purpose of modeling and analyzing decision-making in situations with multiple stakeholders. Specifically, since a waste management model is sustainable when considering not only environmental and economic but also social aspects, the waste management bargaining game is introduced as a specific decision support framework in which future models can be developed

Decision support models for solid waste management: Review and game-theoretic approaches

Energy Technology Data Exchange (ETDEWEB)

Karmperis, Athanasios C., E-mail: athkarmp@mail.ntua.gr [Sector of Industrial Management and Operational Research, School of Mechanical Engineering, National Technical University of Athens, Iroon Polytechniou 9, 15780 Athens (Greece); Army Corps of Engineers, Hellenic Army General Staff, Ministry of Defence (Greece); Aravossis, Konstantinos; Tatsiopoulos, Ilias P.; Sotirchos, Anastasios [Sector of Industrial Management and Operational Research, School of Mechanical Engineering, National Technical University of Athens, Iroon Polytechniou 9, 15780 Athens (Greece)

2013-05-15

Highlights: ► The mainly used decision support frameworks for solid waste management are reviewed. ► The LCA, CBA and MCDM models are presented and their strengths, weaknesses, similarities and possible combinations are analyzed. ► The game-theoretic approach in a solid waste management context is presented. ► The waste management bargaining game is introduced as a specific decision support framework. ► Cooperative and non-cooperative game-theoretic approaches to decision support for solid waste management are discussed. - Abstract: This paper surveys decision support models that are commonly used in the solid waste management area. Most models are mainly developed within three decision support frameworks, which are the life-cycle assessment, the cost–benefit analysis and the multi-criteria decision-making. These frameworks are reviewed and their strengths and weaknesses as well as their critical issues are analyzed, while their possible combinations and extensions are also discussed. Furthermore, the paper presents how cooperative and non-cooperative game-theoretic approaches can be used for the purpose of modeling and analyzing decision-making in situations with multiple stakeholders. Specifically, since a waste management model is sustainable when considering not only environmental and economic but also social aspects, the waste management bargaining game is introduced as a specific decision support framework in which future models can be developed.

Improving technical support to IAEA safeguards

International Nuclear Information System (INIS)

Rundquist, D.

1986-01-01

Changes present new safeguards challenges and require that the entire safeguards process become more efficient. A development process has evolved at the Agency that aids in matching appropriate technology to the needs, primarily through the mechanism of voluntary Member States Support Programme, which gives IAEA access to many of the worlds finest nuclear laboratories. The function of these programs is discussed in this article with particular emphasis on the Agency's co-ordination role. Besides a description of the Member States Support Programme the problems involved (coordination and communication aspects) as well as the results achieved are indicated. The support is categorized under the following headlines: 1) Information and expertise; 2) Instrumentation, methods and techniques; 3) Training; 4) Test and calibration facilities. As mentioned in the article Member States also benefit from the Support Programme. Other means of technical support such as multi-national co-operation programmes and bilateral research agreements are mentioned

Technical Support Section annual work plan for FY 1998

Energy Technology Data Exchange (ETDEWEB)

Adkisson, B.P.; Allison, K.L.; Effler, R.P.; Hess, R.A.; Keeble, T.A.; Odom, S.M.; Smelcer, D.R.

1997-12-01

The Technical Support Section (TSS) of the Instrumentation and Controls (I and C) Division of Oak Ridge National Laboratory (ORNL) provides technical services such as fabrication, modification, installation, calibration, operation, repair, and preventive maintenance of instruments and other related equipment. Because the activities and priorities of TSS must be adapted to the technical support needs of ORNL, the TSS Annual Work Plan is derived from, and is driven directly by, current trends in the budgets and activities of each ORNL division for which TSS provides support. Trends that will affect TSS planning during this period are reductions in the staffing levels of some R and D programs because of attrition or budget cuts. TSS does not have an annual budget to cover operating expenses incurred in providing instrument maintenance support to ORNL. Each year, TSS collects information concerning the projected funding levels of programs and facilities it supports. TSS workforce and resource projections are based on the information obtained and are weighted depending on the percentage of support provided to that division or program. Each year, TSS sets the standard hourly charge rate for the following fiscal year. The Long-Range Work Plan is based on estimates of the affects of the long-range priorities and directions of the Laboratory. Proposed new facilities and programs provide additional bases for long-range planning. After identifying long-range initiatives, TSS planning includes future training requirements, reevaluation of qualifications for new hires, and identification of essential test equipment that will be needed for new work.

Technical evaluation of two methods for composting of organic wastes to be used in domestic vegetables gardens

OpenAIRE

Campos-Rodríguez, Rooel; Brenes-Peralta, Laura; Jiménez-Morales, María Fernanda

2016-01-01

The need to achieve organic waste management solutions has led to treatment options of waste like composting. This practice is defined as the transformation of organic wastes by biological means in controlled conditions; the result is a fertilizer or substrate which can be used in agriculture. In this investigation, a technical evaluation of two composting methods to be applied in home vegetable gardens was carried out. The first  method for degrading of residues evaluated consists in the add...

Technical area status report for chemical/physical treatment

International Nuclear Information System (INIS)

Brown, C.H. Jr.; Schwinkendorf, W.E.

1993-08-01

The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs and activities throughout the DOE Complex. The Mixed Waste Integrated Program (MWIP) was created by the DOE Office of Technology Development (OTD) to develop, deploy, and complete appropriate technologies for the treatment of an DOE low-level mixed waste (LLMW). The MWIP mission includes development of strategies related to enhanced waste form production, improvements to and testing of the EM-30 baseline flowsheet for mixed waste treatment, programmatic oversight for ongoing technical projects, and specific technical tasks related to the site specific Federal Facilities Compliance Agreement (FFCA). The MWIP has established five Technical Support Groups (TSGs) based on primary functional areas of the Mixed Waste Treatment Plant) identified by EM-30. These TSGs are: (1) Front-End Waste Handling, (2) Chemical/Physical Treatment, (3) Waste Destruction and Stabilization, (4) Second-stage Destruction and Offgas Treatment, and (5) Final Waste Forms. The focus of this document is the Chemical/Physical Treatment System (CPTS). The CPTS performs the required pretreatment and/or separations on the waste streams passing through the system for discharge to the environment or efficient downstream processing. Downstream processing can include all system components except Front-End Waste Handling. The primary separations to be considered by the CPTS are: (1) removal of suspended and dissolved solids from aqueous and liquid organic streams, (2) separation of water from organic liquids, (3) treatment of wet and dry solids, including separation into constituents as required, for subsequent thermal treatment and final form processing, (4) mercury removal and control, and (5) decontamination of equipment and waste classified as debris

Structure of technical systems: interpersonal networks and performance in nuclear waste and photovoltaic research

International Nuclear Information System (INIS)

Shrum, W.M. Jr.

1982-01-01

The organization of scientific technology in modern, industrialized societies is examined by comparing two large-scale, multi-organizational, mission-oriented research networks. Using national data from personal interviews with 297 scientists, engineers, research managers, and policy makers from 97 organizations involved in nuclear waste management and solar-photovoltaic development, this study develops and tests hypotheses on the relationships among governmental, academic, private, and public interest sectors and the kinds of social linkages which are associated with technical performance. The principal finding is that in photovoltaic research, contacts with the research community are associated with high levels of performance, while for nuclear waste researchers, they are not. Instead, linkages to the governmental sector predict performance in nuclear waste research. This difference is explained by the governmental domination of the nuclear-waste system and the lack of private-sector involvement

Approaches to technical and scientific support for the nuclear regulatory body in Belarus

International Nuclear Information System (INIS)

Lobacha, Dmitry J.; Teskeb, Hartmuth

2010-01-01

Approaches to technical and scientific support for the State NPP Program in Belarus are described and compared with the recommendations of the IAEA. The past infrastructure in Belarus did not have specialized technical support organization (TSO) for the nuclear regulatory body. Currently, there are two technical and scientific support centers, nominated by decrees. They are part of the NPP infrastructure and belong to the National Academy of Sciences and the Ministry of Energy. It is a challenge to establish the needed TSO capacities for the nuclear regulatory body (the Ministry for Emergency Situations) inside existing institutions of the Ministry for Emergency Situations (MES). Initially, the new technical support structure could focus on well known topics like emergency preparedness and radiation protection. The scope of work has to be extended to all major aspects of radiation and nuclear safety of the new NPP soon. National education as well as international knowledge transfer are important for that. Tasks and challenges of new technical safety institution(s) are described. (author)

TECHNICAL DOCUMENT PREPARATION PLAN FOR THE RETRIEVABILITY STRATEGY REPORT

International Nuclear Information System (INIS)

P.D. Gehner

1997-01-01

The objective of this systems study is to produce a waste removability strategy document that contains sufficient details, recommended design alternatives, and the technical rationale (a) to support Licensing in the development of the License Application Plan, and (b) to provide input in the form of design requirements, for the FY 97 Retrieval Design & Operation activity in support of viability assessment. The intent of this systems study is to support a decision on how to proceed with design with respect to retrievability, regarding the extent to which the repository/waste package designs should accommodate the retrieval option

Technical and socio-political issues in radioactive waste disposal 1986. Vol. 1

International Nuclear Information System (INIS)

Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

1987-11-01

The purpose of the study was to provide an integrated technical and socio-political analysis of how six countries (Federal Republic of Germany, France, Sweden, Switzerland, United Kingdom and the United States of America) have responded to four key issues in radioactive waste management: a) What constitutes 'safe' or 'absolutely safe' disposal, b) site selection processes, c) timing and type of interim storage. (orig./HP)

TECHNICAL GUIDANCE DOCUMENT: CONSTRUCTION QUALITY MANAGEMENT FOR REMEDIAL ACTION AND REMEDIAL DESIGN WASTE CONTAINMENT SYSTEMS

Science.gov (United States)

This Technical Guidance Document is intended to augment the numerous construction quality control and construction quality assurance (CQC and CQA) documents that are available far materials associated with waste containment systems developed for Superfund site remediation. In ge...

Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Tuite, P.; Tuite, K.; Harris, G.

1994-09-01

This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases

Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, Fiscal Year 1986

International Nuclear Information System (INIS)

1986-11-01

The multidisciplinary project was initiated in fiscal year 1986. It comprises two major interrelated parts: (1) Technical Assistance. This part of the project includes: (a) review of the progress of major projects in the DOE Office of Civilian Radioactive Waste Management Program and advise the Engineering and Geotechnology Division on significant technical issues facing each project; (b) analyze geotechnical data, reports, tests, surveys and plans for the different projects; (c) review and comment on major technical reports and other program documents such as site characterization plans and area characterization plans and (d) provide scientific and technical input at technical meetings. (2) Topical Studies. This activity comprises studies on scientific and technical topics, and issues of significance to in-situ testing, test analysis methods, and performance assessment of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. For fiscal year 1986, one minor and one major area of investigation were undertaken. The minor topic is a preliminary consideration and planning exercise for post-closure monitoring studies. The major topic, with subtasks involving various geoscience disciplines, is on the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses. The present report lists the technical reviews and comments made during the fiscal year and summarizes the technical progress of the topical studies

Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-01-01

The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete

International Nuclear Information System (INIS)

Gidarakos, E.; Havas, G.; Ntzamilis, P.

2006-01-01

A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands

Municipal solid waste composition determination supporting the integrated solid waste management system in the island of Crete.

Science.gov (United States)

Gidarakos, E; Havas, G; Ntzamilis, P

2006-01-01

A one-year survey was conducted in the greater region of Crete (located at the lower region of the Aegean Sea) for the purpose of identifying waste composition (including chemical and physical characterization), as well as any seasonal variation. The investigation was carried out repeatedly at seven landfills and one transfer station in Crete, in four phases. Each sampling phase corresponded to a season (autumn, winter, spring, summer). ASTM D5231-92(2003) standard method and RCRA Waste Sampling Draft Technical Guidance were used. Hand sorting was used for classifying the collected wastes into the following categories: plastics, paper, metals, aluminium, leather-wood-textiles-rubbers, organic wastes, non-combustibles and miscellaneous. Further analysis included proximate and ultimate analysis of combustible materials. Metals such as lead, cadmium and mercury were also investigated. The results show that there has been a significant decrease of organic wastes during the last decade due to the increase of packaging materials, as a result of a change in consumption patterns. Three main waste categories were determined: organic wastes, paper and plastics, which combined represent 76% of the total waste in Crete. Furthermore, a high fraction of glass and a seasonal variation of aluminium indicate a strong correlation of waste composition with certain human activities, such as tourism. There is also a variation between the municipal solid waste (MSW) composition in the region of Crete (2003-2004) and MSW composition suggested in the National Solid Waste Planning (2000) [National Solid Waste Planning, 2000. Completion and particularization of Common Ministerial Act 113944//1944/1997: National Solid Waste Planning, June 2000]. The results of this survey are to be utilized by the regional solid waste authorities in order to establish an integrated waste treatment site, capable of fulfilling the regional waste management demands.

Process Waste Assessment for the Plotting and Digitizing Support Laboratory

International Nuclear Information System (INIS)

Phillips, N.M.

1994-04-01

This Process Waste Assessment was conducted to evaluate the Plotting and Digitizing Support Laboratory, located in Building 913, Room 157. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility

Waste processing to support 99Mo production at Sandia National Laboratories

International Nuclear Information System (INIS)

Longley, S.; Carson, S.; McDonald, M.

1997-01-01

As part of the isotope production program at Sandia National Laboratories (SNL), procedures are being finalized for the production of 99 Mo from the irradiation of 235 U-coated stainless-steel targets at the Technical Area (TA) V reactor and hot-cell facilities. Methods have been identified and tested for the management of the nonproduct (waste) material as the final step in the production process. These methods were developed utilizing the waste material from a series of cold and hot tests, beginning with depleted uranium powder and culminating with a test involving an irradiated 235 U target with an initial fission product inventory of ∼18000 Ci at the end of the irradiation cycle. This paper describes the radioactive waste management from the isotope production

Hanford sitewide grounwater remediation - supporting technical information

International Nuclear Information System (INIS)

Chiaramonte, G.R.

1996-05-01

The Hanford Sitewide Groundwater Remediation Strategy was issued in 1995 to establish overall goals for groundwater remediation on the Hanford Site. This strategy is being refined to provide more detailed justification for remediation of specific plumes and to provide a decision process for long-range planning of remediation activities. Supporting this work is a comprehensive modeling study to predict movement of the major site plumes over the next 200 years to help plan the remediation efforts. The information resulting from these studies will be documented in a revision to the Strategy and the Hanford Site Groundwater Protection Management Plan. To support the modeling work and other studies being performed to refine the strategy, this supporting technical information report has been produced to compile all of the relevant technical information collected to date on the Hanford Site groundwater contaminant plumes. The primary information in the report relates to conceptualization of the source terms and available history of groundwater transport, and description of the contaminant plumes. The primary information in the report relates to conceptualization of the source terms and available history of groundwater transport, description of the contaminant plumes, rate of movement based on the conceptual model and monitoring data, risk assessment, treatability study information, and current approach for plume remediation

Regular Recycling of Wood Ash to Prevent Waste Production (RecAsh). Technical Final Report

Energy Technology Data Exchange (ETDEWEB)

Andersson, Lars E-mail: lars.t.andersson@skogsstyreslen.se

2007-03-15

At present, the extraction of harvest residues is predicted to increase in Sweden and Finland. As an effect of the intensified harvesting, the export of nutrients and acid buffering substances from the growth site is also increased. Wood ash could be used to compensate forest soils for such losses. Most wood fuel ash is today often deposited in landfills. If the wood ash is recycled, wood energy is produced without any significant waste production. Ash recycling would therefore contribute to decreasing the production of waste, and to maintaining the chemical quality of forest waters and biological productivity of forest soils in the long term. The project has developed, analysed and demonstrated two regular ash-recycling systems. It has also distributed knowledge gathered about motives for ash recycling as well as technical and administrative solutions through a range of media (handbooks, workshops, field demonstrations, reports, web page and information videos). Hopefully, the project will contribute to decreasing waste problems related to bio-energy production in the EU at large. The project has been organised as a separate structure at the beneficiary and divided in four geographically defined subprojects, one in Finland and three in Sweden (Central Sweden, Northern Sweden, and South-western Sweden). The work in each subproject has been lead by a subproject leader. Each subproject has organised a regional reference group. A project steering committee has been established consisting of senior officials from all concerned partners. The project had nine main tasks with the following main expected deliverables and output: 1. Development of two complete full-scale ash-recycling systems; 2. Production of handbooks of the ash recycling system; 3. Ash classification study to support national actions for recommendations; 4. Organise regional demonstrations of various technical options for ash treatment and spreading; 5. Organise national seminars and demonstrations of

Buckling design criteria for waste package disposal containers in mined salt repositories: Technical report

International Nuclear Information System (INIS)

Mallett, R.H.

1986-12-01

This report documents analytical and experimental results from a survey of the technical literature on buckling of thick-walled cylinders under external pressure. Based upon these results, a load factor is suggested for the design of waste package containers for disposal of high-level radioactive waste in repositories mined in salt formations. The load factor is defined as a ratio of buckling pressure to allowable pressure. Specifically, a load factor which ranges from 1.5 for plastic buckling to 3.0 for elastic buckling is included in a set of proposed buckling design criteria for waste disposal containers. Formulas are given for buckling design under axisymmetric conditions. Guidelines are given for detailed inelastic buckling analyses which are generally required for design of disposal containers

A Theory of Sex Differences in Technical Aptitude and Some Supporting Evidence.

Science.gov (United States)

Schmidt, Frank L

2011-11-01

In this article, I present a theory that explains the origin of sex differences in technical aptitudes. The theory takes as proven that there are no sex differences in general mental ability (GMA), and it postulates that sex differences in technical aptitude (TA) stem from differences in experience in technical areas, which is in turn based on sex differences in technical interests. Using a large data set, I tested and found support for four predictions made by this theory: (a) the construct level correlation between technical aptitude and GMA is larger for females than males, (b) the observed and true score variability of technical aptitude is greater among males than females, (c) at every level of GMA females have lower levels of technical aptitude, and (d) technical aptitude measures used as estimates of GMA for decision purposes would result in underestimation of GMA levels for girls and women. Given that GMA carries the weight of prediction of job performance, the support found for this last prediction suggests that, for many jobs, technical aptitude tests may underpredict the job performance of female applicants and employees. Future research should examine this question. © Association for Psychological Science 2011.

The Office of Environmental Management technical reports: A bibliography

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The Office of Environmental Management`s (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1995--that were published from October 1, 1996--September 30, 1997. This information is divided into the following categories: Miscellaneous, Focus Areas and Crosscutting Programs, Support Programs, Technology Integration and International Technology Exchange, are now included in the Miscellaneous category. The Office of Environmental Management within the Department of Energy (DOE) is responsible for environmental restoration, waste management, technology development and facility transition and management. Subjects include: subsurface contaminants; mixed waste characterization, treatment and disposal; radioactive tank waste remediation; plutonium; deactivation and decommissioning; robotics; characterization, monitoring, and sensor technology; and efficient separations. 880 refs.

Technical program plan, Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1979-12-01

The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included

Technical Support for the development of DCS

Energy Technology Data Exchange (ETDEWEB)

Oh, In Seok; Lee, Cheol Kwon; Kim, Dong Hoon; Kim, Jung Taek; Hwang, In Koo; Park, Jae Chang; Lee, Dong Young; Park, Won Man

2008-05-15

The objective of this project is to provide a technical support to Woori Tech Co. in its design and manufacture process of the DCS as a part of KNICS development program to promote the technology self-reliance for non-safety equipment for NPPs(Nuclear Power Plants). We support Woori Tech Co. to develop a DCS which satisfies the requirements for Shinkori 3 and 4 NPPs in the aspects of reliability, applicability and technical competitiveness. As the results of this project the following items were developed and/or implemented; {center_dot} Design basis and requirements for a DCS system {center_dot} Design requirements for control communication networks {center_dot} Architecture of control networks {center_dot} Design requirements of EWS(Engineering Workstation) {center_dot} Plan of software verification and validation {center_dot} Operation display design {center_dot} Soft control functions {center_dot} Application development tools of DCS {center_dot} Analysis and V/V activities on DCS control network protocols {center_dot} Software verification and validation and documentation guidelines {center_dot} User manual documents.

Underground storage of nuclear waste

International Nuclear Information System (INIS)

Russell, J.E.

1977-06-01

The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commerical radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects. 7 refs., 5 figs

Underground storage of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Russell, J E

1977-12-01

The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commercial radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects.

Implementation of technical conservatism in the development of nuclear waste repositories

International Nuclear Information System (INIS)

Carbiener, W.A.; Hall, R.J.; Matthews, S.C.

1981-01-01

Implementation of the Department of Energy program policy on technical conservatism takes two forms - conservatism in the conduct of the program, and conservatism in the performance of the disposal system. The first is achieved by a stepwise approach to system development and operation, the systems (multibarrier) viewpoint, the retrievability requirement, and the extensive use of peer reviews throughout the conduct of the program. The second is achieved by the proper selection and application of conservative design and operational limits. This paper discusses each approach individually. The inherent uncertainties associated with geologic disposal of nuclear waste dictate that conservatism be prudently applied in the conduct of the program, in the disposal system design, analysis, and performance, and in applying current mining technology to waste disposal. An example is presented to illustrate an approach to establishing design margins

Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Eibling, R.E.

2001-07-26

The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site`s centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million.

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site's centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million

Solid waste burial grounds interim safety analysis

International Nuclear Information System (INIS)

Saito, G.H.

1994-01-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

Solid waste burial grounds interim safety analysis

Energy Technology Data Exchange (ETDEWEB)

Saito, G.H.

1994-10-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

The INR program in 2000-2005 period for developing the national technical support of the nuclear power

International Nuclear Information System (INIS)

Gheorghiu, C.

2001-01-01

The INR - Pitesti is largely implied in implementing the tasks of high complexity stipulated by the Emergency Directive of the Romanian Government No. 144/30.09.1999 meant to ensure the national technical support for the nuclear power field as well as the development of presupposed international cooperation. The Strategic Program of the Autonomous Authority for Nuclear Activities (RAAN) stipulates the main activities to be carried-out in the period 2000-2005 and beyond, in the frame of 18 specific programs. These programs approaches high priority world wide issues targeting major objectives like efficient operation of NPPs ensuring the design service life, creating conditions for extension of operation duration increasing the safety standard of personnel, of population as well as reducing the impact of nuclear power upon the environmental. Also, the program approaches functionally the problem of safety management of the radioactive waste resulting from nuclear facility operation. Achieving these major objective as well as of those specific laid down in the Strategic Program requires continual supply with material and human resources, refurbishment of material background of INR in its research and development activities as well as a consistent integration of the INR staff of researchers within the international scientific community. Implementing the annual programs included in the Strategic Program will ensure also fulfilment of the international arrangements of our country as well as the realization of the agreements concluded by the Ministry of Industry and Resources and RAAN with analogous authorities from abroad (AECL - Canada, DOE - USA, etc.). This document has the following content: 1. Legislative support and the mission of the program; 2. Program's strategic objectives; 3. General technical objectives of the programs. 4. Financing; 5. Providing and training human resources; 6. Investments for research and development; 7. International cooperation; 8

Central Waste Complex (CWC) essential/support drawing list

International Nuclear Information System (INIS)

WHITLOCK, R.W.

1999-01-01

Essential and supporting engineering drawings for the Central Waste Complex (CWC) are identified in this document. The purpose of the document is to describe the criteria used to identify drawings and the plan for updating and maintaining their accuracy. This document supports HNF-PRO-242 and HNF-PRO-440

Research and technology programmes supporting waste management in BNFL

International Nuclear Information System (INIS)

Fairhall, G.A.; Horner, A.M.

2000-01-01

Waste Management is a major activity of BNFL in the UK and at various locations internationally. To support these activities extensive programmes of Research and Technology have been undertaken for many years. This involves practical studies involving active and non-active work at laboratory and pilot plant scale. Extensive use is also made of theoretical and modelling techniques. Current work is aimed at underpinning and improving current operations supporting the design and safety cases of new plant and addressing waste management activities of the future including decommissioning. (authors)

Conversion of transuranic waste to low level waste by decontamination: a technical and economic evaluation

International Nuclear Information System (INIS)

Allen, R.P.; Hazelton, R.F.

1984-12-01

A study was conducted to evaluate the technical and economic feasibility of using in-situ decontamination techniques to convert glove boxes and other large TRU-contaminated components directly into LLW. The results of the technical evaluation indicate that in-situ decontamination of these types of components to non-TRU levels is technically feasible. Applicable decontamination techniques include electropolishing, hand scrubbing, chemical washes/sprays, strippable coatings and Freon spray-cleaning. The removal of contamination from crevices and other holdup areas remains a problem, but may be solved through further advances in decontamination technology. Also, the increase in the allowable maximum TRU level from 10 nCi/g to 100 nCi/g as defined in DOE Order 5820.2 reduces the removal requirement and facilitates measurement of the remaining quantities. The major emphasis of the study was on a cost/benefit evaluation that included a review and update of previous analyses and evaluations of TRU-waste volume reduction and conversion options. The results of the economic evaluation show, for the assumptions used, that there is a definite cost incentive to size reduce large components, and that decontamination of sectioned material has become cost competitive with the size reduction options. In-situ decontamination appears to be the lowest cost option when based on routine-type operations conducted by well-trained and properly equipped personnel. 16 references, 1 figure, 7 tables

IAEA Safeguards and technical support programs: POTAS in the 1990s

International Nuclear Information System (INIS)

Kessler, C.J.

1991-01-01

The US Program of Technical Assistance to IAEA Safeguards (POTAS) has since 1978 provided technology and technical assistance to the IAEA to support its nuclear safeguards activities. The present level of support, $6.9 million per year, equals 10% of the Department of Safeguards annual budget. During the next decade, the International Atomic Energy Agency (IAEA) will face new technical challenges in carrying out its verification activities. To help the IAEA acquire the technology and other technical support that it will require in the 1990s, POTAS expects to continue its assistance, both in the areas established in the past and in additional areas dictated by newly identified IAEA safeguards requirements. This paper will look at the political and policy context within which the Department of Safeguards, and hence POTAS, operates, and how that context is expected to evolve over the next decade. The roles and functions of POTAS will be identified and discussed in terms of their historical evolution. Lastly, the paper will consider how POTAS is expected to change during the 1990s, both to maintain effectiveness in existing roles and functions, and to meet the challenge of the changing policy context. 5 refs

IAEA co-ordinated technical support programme to the NIS

International Nuclear Information System (INIS)

Olsen, R.; Murakami, K.; Blacker, C.; Sharma, S.K.

1999-01-01

With most Newly Independent States (NIS) of the former Soviet Union becoming parties to the Non-Proliferation Treaty as Non-Nuclear Weapon States, there has been an acute need in these states for considerable assistance for the establishment of the necessary structure and resources to ensure that their commitments to non-proliferation are fully implemented in a timely manner. A number of IAEA Member States have offered and are now providing assistance to the NIS on a bilateral level to set up an appropriate State System of Accounting and Control (SSAC) which includes Import/Export Control and Physical Protection of Nuclear Material in each state. The IAEA and these Member States established the Co-ordinated Technical Support Programme (CTSP) to ensure that the support given to the NIS was done in a co-ordinated and transparent manner and to avoid duplication of effort. The IAEA has played a coordinating role for the past 5 years by helping to identify detailed needs in individual States, by providing a platform for Member States to identify areas where they could provide the optimum support, and in developing and preparing the Co-ordinated Technical Support Plans. The IAEA organises annual meetings in Vienna attended by all donor and recipient countries to review the focus and implementation status of the co-ordinated technical support activities. A position statement is made by each donor and recipient country, and views and experiences are exchanged. The contents of the CTSPs and the role of the Agency in monitoring the progress of the individual tasks are reviewed in this paper. A summary comparing the implementation status of the Programme by each country is presented. (author)

Generation of organic waste from institutions in Denmark: case study of the Technical University of Denmark

DEFF Research Database (Denmark)

Edjabou, Maklawe Essonanawe; Boldrin, Alessio; Scheutz, Charlotte

at least 60% of organic waste – that cannot be prevented or reduced –generated by service sector, should be source-segregated and collected separately. In order to establish the baseline of the current situation, and to allow for any evaluation of performance against target indicators, data on solid waste...... generation and composition are required. The overall aim of this study was to quantify the potential for source-segregated organic waste as well as mixed waste from institution. This study was carried at the Department of Environmental Engineering at Technical University of Denmark. In the course...... and public holidays, when the offices were officially closed. Furthermore, the composition of source-segregated organic waste was analysed to investigate its purity. During the sampling period, the number of employees coming to work at the department was recorded. These data were used to investigate any...

TMI-2 Technical Information and Examination Program. 1984 annual report

International Nuclear Information System (INIS)

Hess, C.J.

1985-04-01

In 1984, the US Department of Energy's Technical Information and Examination Program entered its fifth year of research and development work at Three Mile Island Unit 2 (TMI-2) and at the Idaho National Engineering Laboratory and other supporting laboratories. The work concentrated on six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition

Scoping evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Examples: Sandia National Laboratories and Los Alamos National Laboratory

International Nuclear Information System (INIS)

Gruebel, M.R.; Parsons, A.M.; Waters, R.D.

1996-01-01

The disposal of mixed low-level waste has become an issue for the U.S. Department of Energy and the States since the inception of the Federal Facilities Compliance Act in 1992. Fifteen sites, including Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL), have been evaluated to estimate their technical capabilities for disposal of this type of waste after it has been subjected to treatment processes. The analyses were designed to quantify the maximum permissible concentrations of radioactive and hazardous constituents in mixed low-level waste that could potentially be disposed of in a facility at one of the fifteen sites and meet regulatory requirements. The evaluations provided several major insights about the disposal of mixed low-level waste. All of the fifteen sites have the technical capability for disposal of some waste. Maximum permissible concentrations for the radioactive component of the waste at and sites such as SNL and LANL are almost exclusively determined by pathways other than through groundwater. In general, for the hazardous component of the waste, travel times through groundwater to a point 100 meters from the disposal facility are on the order of thousands of years. The results of the evaluations will be compared to actual treated waste that may be disposed of in a facility at one of these fifteen evaluated sites. These comparisons will indicate which waste streams may exceed the disposal limitations of a site and which component of the waste limits the technical acceptability for disposal. The technical analyses provide only partial input to the decision-making process for determining the disposal sites for mixed low-level waste. Other, less quantitative factors such as social and political issues will also be considered

Geological Disposal of Radioactive Waste: A Long-Term Socio-Technical Experiment.

Science.gov (United States)

Schröder, Jantine

2016-06-01

In this article we investigate whether long-term radioactive waste management by means of geological disposal can be understood as a social experiment. Geological disposal is a rather particular technology in the way it deals with the analytical and ethical complexities implied by the idea of technological innovation as social experimentation, because it is presented as a technology that ultimately functions without human involvement. We argue that, even when the long term function of the 'social' is foreseen to be restricted to safeguarding the functioning of the 'technical', geological disposal is still a social experiment. In order to better understand this argument and explore how it could be addressed, we elaborate the idea of social experimentation with the notion of co-production and the analytical tools of delegation, prescription and network as developed by actor-network theory. In doing so we emphasize that geological disposal inherently involves relations between surface and subsurface, between humans and nonhumans, between the social, material and natural realm, and that these relations require recognition and further elaboration. In other words, we argue that geological disposal concurrently is a social and a technical experiment, or better, a long-term socio-technical experiment. We end with proposing the idea of 'actor-networking' as a sensitizing concept for future research into what geological disposal as a socio-technical experiment could look like.

Technical issues for WIPP

International Nuclear Information System (INIS)

Hunter, T.O.

1979-01-01

Emplacement of wastes in the WIPP will include experiments on various waste types which will provide essential data on waste-rock interaction and repository response. These experiments will include evolution of the synergistic effects of both heat production, radiation, and actual waste forms. While these studies will provide essential data on the validity of waste isolation in bedded salt, they will be preceded by a broad-based experimental program which will resolve many of the current technical issues providing not only an assessment of the safety of performing such experiments but also the technical basis for assurance that the appropriate experiments are performed. Data and predictive modeling techniques, which are currently available, can bound the consequences associated with these technical issues. Predictions of the impact on public safety based on these analyses indicate that safe waste disposal in WIPP salt beds is achievable; however, a major use of WIPP will be to conduct realistic experiments with HLW forms to address some of the unresolved details of these waste/salt interactions

Supporting the initiative. Cooperation in radioactive waste management with the Russian Federation

International Nuclear Information System (INIS)

Bonne, A.; Semenov, B.

2000-01-01

An important objective of the IAEA activities is to facilitate and strengthen international co-operation for the sound and safe management of radioactive waste and spent nuclear fuel. The Russian Federation has been facing a number of complicated environmental problems in this field. This article gives a brief overview of the activities of the Contact Expert Group (CEG) which was established in 1996 with the objectives to promote international co-operative efforts aimed at resolving radioactive waste management issues, including radiation safety, environmental, technical, legal, organizational and financial matters

Preliminary data from an instantaneous profile test conducted near the Mixed Waste Landfill, Technical Area 3, Sandia National Laboratories/New Mexico

International Nuclear Information System (INIS)

Bayliss, S.C.; Goering, T.J.; McVey, M.D.; Strong, W.R.; Peace, J.L.

1996-04-01

This paper presents data from an instantaneous profile test conducted near the Sandia National Laboratories/New Mexico Mixed Waste Landfill in Technical Area 3. The test was performed from December 1993 through 1995 as part of the environmental Restoration Project's Phase 2 RCRA Facility Investigation of the Mixed Waste Landfill. The purpose of the test was to measure the unsaturated hydraulic properties of soils near the Mixed Waste Landfill. The instantaneous profile test and instrumentation are described, and the pressure and moisture content data from the test are presented. These data may be useful for understanding the unsaturated hydraulic properties of soils in Technical Area 3 and for model validation, verification, and calibration

Educational initiatives in environmental restoration and waste management

International Nuclear Information System (INIS)

Prestwich, S.M.

1990-01-01

Policy-makers responding to the urgency of the demands for a clean environment are finding that America lacks the technical know-how and the pool of technicians, scientists, and engineers to meet the environmental challenges. In response to the need for a technically skilled work force, government agencies and the private sector have worked to assess the probable effect of shortages and have sought ways to prevent the problem. The US Department of Energy (DOE) and its predecessor agencies have historically supported strong linkages between the academic community - the providers of scientists and engineers - and the department - the users of those workers - to assure an adequate supply of appropriately educated technicians, scientists, and engineers to conduct basic and applied research in support of the DOE's mission and to implement that mission. One of the department's challenges is the minimization, management, and cleanup of waste materials generated from departmental operations. The recently published Environmental Restoration and Waste Management Five-Year Plan for fiscal years 1992 through 1996 reaffirms DOE's policy of compliance with environmental laws and regulations. It also maps out the newly created Office of Environmental Restoration and Waste Management's aggressive programs to improve training and education, to arouse interest in pursuit of science/engineering careers, and to place special emphasis on recruiting minorities and women to technical fields vital to the environmental restoration/waste management mission

Draft federal GHG accounting and reporting : technical support document

Science.gov (United States)

2010-07-01

This is a technical support document (TSD) that accompanies the Federal Greenhouse Gas Accounting and Reporting Guidance (or Guidance). This document provides detailed information on the inventory reporting process and accepted calculation methodolog...

Customer service model for waste tracking at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Dorries, Alison M.; Montoya, Andrew J.; Ashbaugh, Andrew E.

2010-01-01

The deployment of any new software system in a production facility will always face multiple hurtles in reaching a successful acceptance. However, a new waste tracking system was required at the plutonium processing facility at Los Alamos National Laboratory (LANL) where waste processing must be integrated to handle Special Nuclear Materials tracking requirements. Waste tracking systems can enhance the processing of waste in production facilities when the system is developed with a focus on customer service throughout the project life cycle. In March 2010 Los Alamos National Laboratory Waste Technical Services (WTS) replaced the aging systems and infrastructure that were being used to support the plutonium processing facility. The Waste Technical Services (WTS) Waste Compliance and Tracking System (WCATS) Project Team, using the following customer service model, succeeded in its goal to meet all operational and regulatory requirements, making waste processing in the facility more efficient while partnering with the customer.

The formation of technic soil in a revegetated uranium ore waste rock pile (Limousin, France)

Science.gov (United States)

Boekhout, Flora; Gérard, Martine; Kanzari, Aisha; Calas, Georges; Descostes, Michael

2014-05-01

Mining took place in France between 1945 and 2001 during which time ~210 different sites were exploited and/or explored. A total of 76 Kt of uranium was produced, 52 Mt of ore was extracted, but also 200 Mt of waste rocks was produced, the majority of which, with uranium levels corresponding to the natural environment. So far, the processes of arenisation and technic soil formation in waste rock piles are not well understood but have important implications for understanding the environmental impact and long-term speciation of uranium. Understanding weathering processes in waste rock piles is essential to determine their environmental impact. The main objectives of this work are to assess 1) the micromorphological features and neo-formed U-bearing phases related to weathering and 2) the processes behind arenisation of the rock pile. The site that was chosen is the Vieilles Sagnes waste rock pile in Fanay (Massif Central France) that represents more or less hydrothermally altered granitic rocks that have been exposed to weathering since the construction of the waste rock pile approximately 50 years ago. Two trenches were excavated to investigate the vertical differentiation of the rock pile. This site serves as a key location for studying weathering processes of waste rock piles, as it has not been reworked after initial construction and has therefore preserved information on the original mineralogy of the waste rock pile enabling us to access post emplacement weathering processes. The site is currently overgrown by moss, meter high ferns and small trees. At present day the rock pile material can be described as hydrothermally altered rocks and rock fragments within a fine-grained silty clay matrix exposed to surface conditions and weathering. A sandy "paleo" technic soil underlies the waste rock pile and functions as a natural liner by adsorption of uranium on clay minerals. Post-mining weathering of rock-pile material is superimposed on pre-mining hydrothermal and

Engineering Technical Support Center Annual Report Fiscal Year 2016

Science.gov (United States)

This report highlights significant projects that the ETSC supported in fiscal year 2016. These projects have addressed an array of environmental scenarios, including, but not limited to remote mining contamination, expansive landfill waste, cumulative impacts from multiple contam...

Technical basis for a minimum hydroxide concentration in tanks containing dilute waste

International Nuclear Information System (INIS)

Zapp, P.E.

1995-05-01

Laboratory tests were performed to address the protection of waste tank steel from corrosion in situations of elevated temperatures up to 75 C (hot spots) in the sludge layer of Extended Sludge Processing (ESP) tanks. Coupon immersion tests were conducted at 75 C in two ESP simulants at four hydroxide (or pH) levels. The nitrite concentrations of the simulants were calculated from the ESP technical standards based on a temperature of 40 C. The results showed that a hydroxide concentration of at least 0.01 M prevented significant corrosion of the steel at the elevated temperature. This conclusion provides the technical basis for the revised minimum hydroxide concentration of 0.01 M in the draft WSRC 241-82H Control Room Process Requirements, for the ESP tanks

Buried Waste Integrated Demonstration Strategy Plan

International Nuclear Information System (INIS)

Kostelnik, K.M.

1993-02-01

The Buried Waste Integrated Demonstration (BWID) supports the applied research, development, demonstration, and evaluation of a suite of advanced technologies that form a comprehensive remediation system for the effective and efficient remediation of buried waste. These efforts are identified and coordinated in support of the US Department of Energy (DOE), Environmental Restoration and Waste Management (ERWM) needs and objectives. The present focus of BWID is to support retrieval and ex situ treatment configuration options. Future activities will explore and support containment and stabilization efforts in addition to the retrieval/ex situ treatment options. Long and short term strategies of the BWID are provided. Processes for identifying technological needs, screening candidate technologies for BWID applicability, researching technical issues, field demonstrating technologies, evaluating demonstration results to determine each technology's threshold of capability, and commercializing successfully demonstrated technologies for implementation for environmental restoration also are presented in this report

International co-operation for safe radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

As a specialised inter-governmental body, NEA pursues three main objectives for its radioactive waste management programme: - The promotion of studies to improve the data base available in support of national programmes. - The support of Research and Development through co-ordination of national activities and promotion of international projects. - An improvement in the general level of understanding of waste management issues and options, particularly in the field of waste disposal. The management of radioactive waste from nuclear activities covers several sequences of complex technical operations. However, as the ultimate objective of radioactive waste management is the disposal of the waste, the largest part of the work programme is directed towards the analysis of disposal options. In addition, NEA is active in various other areas of waste management, such as the treatment and conditioning of waste, the decommissioning of nuclear facilities and the institutional aspects of the long term management of radioactive waste

Data Quality Objectives for Tank Farms Waste Compatibility Program

International Nuclear Information System (INIS)

BANNING, D.L.

1999-01-01

There are 177 waste storage tanks containing over 210,000 m 3 (55 million gal) of mixed waste at the Hanford Site. The River Protection Project (RPP) has adopted the data quality objective (DQO) process used by the U.S. Environmental Protection Agency (EPA) (EPA 1994a) and implemented by RPP internal procedure (Banning 1999a) to identify the information and data needed to address safety issues. This DQO document is based on several documents that provide the technical basis for inputs and decision/action levels used to develop the decision rules that evaluate the transfer of wastes. A number of these documents are presently in the process of being revised. This document will need to be revised if there are changes to the technical criteria in these supporting documents. This DQO process supports various documents, such as sampling and analysis plans and double-shell tank (DST) waste analysis plans. This document identifies the type, quality, and quantity of data needed to determine whether transfer of supernatant can be performed safely. The requirements in this document are designed to prevent the mixing of incompatible waste as defined in Washington Administrative Code (WAC) 173-303-040. Waste transfers which meet the requirements contained in this document and the Double-Shell Tank Waste Analysis Plan (Mulkey 1998) are considered to be compatible, and prevent the mixing of incompatible waste

Historical review of waste management and recycling in South Africa

CSIR Research Space (South Africa)

Godfrey, Linda

2017-10-01

Full Text Available this instrument was never utilised. Limited waste policy and regulation emerged between 1989 and 2007. With the publishing of the 1st National Waste Management Strategy (NWMS) [3] and the White Paper on Integrated Pollution and Waste Management (IP&WM) [4..., classification and disposal of waste, was developed with funding and technical support from the Danish Cooperation for Environment and Development (DANCED). The Minimum Requirements were replaced by “National Norms and Standards for the Assessment of Waste...

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

Proceedings of the research conference on post-accident waste management safety (RCWM2016) and the technical seminar on safety research for radioactive waste storage

International Nuclear Information System (INIS)

Motooka, Takafumi; Yamagishi, Isao

2017-03-01

Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Post-accident Waste Management Safety (RCWM2016) on 7th November, 2016 and the Technical Seminar on Safety Research for Radioactive Waste Storage on 8th November, 2016. This report compiles the abstracts and the presentation materials in the above conference and seminar. (author)

Vision and framework for technical and management support to facilitate foreign spent fuel storage and geologic disposal in Russia

International Nuclear Information System (INIS)

Halsey, W.G.; Jardine, L.J.; Smith, C.F.

1999-01-01

This 'Technical and Management Support' program would facilitate the transfer of spent fuel from commercial power plants in Taiwan to a storage and geologic repository site near Krasnoyarsk, Russia. This program resolves issues of disposition of Taiwan spent fuel (including US origin fuel) and provides revenue for Russia to develop an integrated spent fuel storage and radioactive waste management system including a geologic repository. LLNL has ongoing contracts and collaborations with all the principal parties and is uniquely positioned to facilitate the development of such a program. A three-phase approach over 20 years is proposed: namely, an initial feasibility investigation followed by an engineering development phase, and then implementation

Radioactive waste management in the United States

International Nuclear Information System (INIS)

Smiley, J.L.

1985-01-01

In the United States, efforts to dispose of the nation's high- and low-level radioactive wastes are based on somewhat different approaches.The individual States are responsible for disposing of low-level wastes with the Federal Government providing technical and financial support to help the States in the early phases of their efforts. The Federal Government has responsibility for developing facilities for the disposal of high-level waste. However, both efforts show a common need to meet national objectives while satisfying the concerns of the public. (author)

Independent technical review, handbook

International Nuclear Information System (INIS)

1994-02-01

Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project

Independent technical review, handbook

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

Purpose Provide an independent engineering review of the major projects being funded by the Department of Energy, Office of Environmental Restoration and Waste Management. The independent engineering review will address questions of whether the engineering practice is sufficiently developed to a point where a major project can be executed without significant technical problems. The independent review will focus on questions related to: (1) Adequacy of development of the technical base of understanding; (2) Status of development and availability of technology among the various alternatives; (3) Status and availability of the industrial infrastructure to support project design, equipment fabrication, facility construction, and process and program/project operation; (4) Adequacy of the design effort to provide a sound foundation to support execution of project; (5) Ability of the organization to fully integrate the system, and direct, manage, and control the execution of a complex major project.

Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

Energy Technology Data Exchange (ETDEWEB)

Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

A Socio-Technical Perspective on Repository Monitoring - 12229

Energy Technology Data Exchange (ETDEWEB)

Bergmans, Anne [University of Antwerp, Faculty of Political and Social Sciences, Sint-Jacobstraat 2, 2000 Antwerpen (Belgium); Elam, Mark; Sundqvist, Goeran [University of Gothenburg, Department of Sociology, Box 720, 40530 Gothenburg (Sweden); Simmons, Peter [University of East Anglia, School of Environmental Sciences, Norwich NR4 7TJ (United Kingdom)

2012-07-01

Monitoring geological repositories for high-activity radioactive wastes has both technical and social dimensions, which are closely interrelated. To investigate the implications of this for geological disposal, data on experts' expectations of repository monitoring and the functions that it is expected to serve were analysed. The analysis drew on strategic and technical documents on monitoring produced by national agencies and by international organisations or projects; interviews with specialists in radioactive waste management organisations on monitoring and on their perceptions of societal concerns and expectations; and observations from technical workshops on repository monitoring. Three main rationales for monitoring were found: performance confirmation; decision support in a step-wise process; and public and stakeholder confidence building. The expectation that monitoring will enhance public confidence is then examined from a social scientific perspective and the potential for and challenges to using monitoring in this way are reviewed. In conclusion, implications for stakeholder engagement in the development of monitoring objectives and strategies are discussed. (authors)

Transformation of technical infrastructure

DEFF Research Database (Denmark)

Nielsen, Susanne Balslev

1998-01-01

article about the need of new planning forums in order to initiate transformations with in management of large technical systems for energy, waste and water supply.......article about the need of new planning forums in order to initiate transformations with in management of large technical systems for energy, waste and water supply....

Fluidized bed steam reformed mineral waste form performance testing to support Hanford Supplemental Low Activity Waste Immobilization Technology Selection

Energy Technology Data Exchange (ETDEWEB)

Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pierce, E. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Burket, P. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, C. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Daniel, W. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fox, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Herman, C. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Miller, D. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, M. F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brown, C. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, N. P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neeway, J. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Valenta, M. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Swanberg, D. J. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Robbins, R. A. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Thompson, L. E. [Washington River Protection Solutions (WRPS), Richland, WA (United States)

2015-10-01

This report describes the benchscale testing with simulant and radioactive Hanford Tank Blends, mineral product characterization and testing, and monolith testing and characterization. These projects were funded by DOE EM-31 Technology Development & Deployment (TDD) Program Technical Task Plan WP-5.2.1-2010-001 and are entitled “Fluidized Bed Steam Reformer Low-Level Waste Form Qualification”, Inter-Entity Work Order (IEWO) M0SRV00054 with Washington River Protection Solutions (WRPS) entitled “Fluidized Bed Steam Reforming Treatability Studies Using Savannah River Site (SRS) Low Activity Waste and Hanford Low Activity Waste Tank Samples”, and IEWO M0SRV00080, “Fluidized Bed Steam Reforming Waste Form Qualification Testing Using SRS Low Activity Waste and Hanford Low Activity Waste Tank Samples”. This was a multi-organizational program that included Savannah River National Laboratory (SRNL), THOR® Treatment Technologies (TTT), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Office of River Protection (ORP), and Washington River Protection Solutions (WRPS). The SRNL testing of the non-radioactive pilot-scale Fluidized Bed Steam Reformer (FBSR) products made by TTT, subsequent SRNL monolith formulation and testing and studies of these products, and SRNL Waste Treatment Plant Secondary Waste (WTP-SW) radioactive campaign were funded by DOE Advanced Remediation Technologies (ART) Phase 2 Project in connection with a Work-For-Others (WFO) between SRNL and TTT.

SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-05-16

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

Protecting safeguards information / Division of technical support

International Nuclear Information System (INIS)

2002-01-01

This DVD contains two films representing the key aspects of the IAEA Department of Safeguards. 'Protecting Safeguards Information' is a narrative/fiction film which presents the Agency's information handling and protection measures. A security representative from a fictional nation receives a briefing on the procedures and methods used by the Department. These techniques will assure member states that the information they provide to the Agency is kept safe and confidential. 'Division of Technical Support' is a non-fiction documentary which presents a detailed look at the technical capabilities and management techniques used by the Agency in nuclear material accountancy. The film covers many aspects of safeguards equipment and techniques including: NDA and DA instruments, seals, surveillance, training, development and maintenance. Taken together, these films provide an introduction and overview to many important aspects of the IAEA Department of Safeguards. (IAEA)

Summary of Conceptual Models and Data Needs to Support the INL Remote-Handled Low-Level Waste Disposal Facility Performance Assessment and Composite Analysis

International Nuclear Information System (INIS)

Sondrup, A. Jeff; Schafter, Annette L.; Rood, Arthur S.

2010-01-01

An overview of the technical approach and data required to support development of the performance assessment, and composite analysis are presented for the remote handled low-level waste disposal facility on-site alternative being considered at Idaho National Laboratory. Previous analyses and available data that meet requirements are identified and discussed. Outstanding data and analysis needs are also identified and summarized. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of facility performance and of the composite performance are required to meet the Department of Energy's Low-Level Waste requirements (DOE Order 435.1, 2001) which stipulate that operation and closure of the disposal facility will be managed in a manner that is protective of worker and public health and safety, and the environment. The corresponding established procedures to ensure these protections are contained in DOE Manual 435.1-1, Radioactive Waste Management Manual (DOE M 435.1-1 2001). Requirements include assessment of (1) all-exposure pathways, (2) air pathway, (3) radon, and (4) groundwater pathway doses. Doses are computed from radionuclide concentrations in the environment. The performance assessment and composite analysis are being prepared to assess compliance with performance objectives and to establish limits on concentrations and inventories of radionuclides at the facility and to support specification of design, construction, operation and closure requirements. Technical objectives of the PA and CA are primarily accomplished through the development of an establish inventory, and through the use of predictive environmental transport models implementing an overarching conceptual framework. This document reviews the conceptual model, inherent assumptions, and data required to implement the conceptual model in a numerical framework. Available site-specific data and data sources

Technical issues in licensing low-level radioactive waste facilities

Energy Technology Data Exchange (ETDEWEB)

Junkert, R. [California Dept. of Health Services, CA (United States)

1993-03-01

The California Department of Health Service spent two years in the review of an application for a low-level radioactive waste disposal facility in California. During this review period a variety of technical issues had to be evaluated and resolved. One of the first issues was the applicability and use of NRC guidance documents for the development of LLW disposal facilities. Other technical issues that required intensive evaluations included surface water hydrology, seismic investigation, field and numerical analysis of the unsaturated zone, including a water infiltration test. Source term verification became an issue because of one specific isotope that comprised more than 90% of the curies projected for disposal during the operational period. The use of trench liners and the proposed monitoring of the unsaturated zone were reviewed by a highly select panel of experts to provide guidance on the need for liners and to ensure that the monitoring system was capable of monitoring sufficient representative areas for radionuclides in the soil, soil gas, and soil moisture. Finally, concerns about the quality of the preoperational environmental monitoring program, including data, sample collection procedures, laboratory analysis, data review and interpretation and duration of monitoring caused a significant delay in completing the licensing review.

Public acceptance in radioactive waste management

International Nuclear Information System (INIS)

Diaconu, Stela; Covreag, Ilinca

2008-01-01

disposal of spent fuel and radioactive waste. National programmes, must give increasing focus not only to the scientific and technical issues, but also to societal, political, legal and economic aspects that influence public perceptions of the safety and feasibility of implementing the disposal concepts. In Romania the National Agency for Radioactive Waste, ANDRAD, drawn-up a public communication strategy which pay an important stress to transparency, openness and accountability issues. This strategy includes an information component and a public involvement one. The public information campaigns will make use of the known communication tools, such as internet, mass-media co-operation, brochures and leaflets dissemination, seminars and conferences. The public involvement in the decision making process will be facilitated through public debates, presentation of the EIA reports, supporting the activity of Local Information Committees and by considering the socio-economic issues related with the repository development programme. Many of these actions have been already started, they are continuously assessed and improved/updated, aiming, together with technical solutions to robust, publicly acceptable projects

Non-technical issues in safety assessments for nuclear disposal facilities

International Nuclear Information System (INIS)

Kallenbach-Herbert, Beate; Brohmann, Bettina

2010-09-01

The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

Urban Waste and Sanitation Services for Sustainable Development: Harnessing social and technical diversity in East Africa

NARCIS (Netherlands)

Vliet, van B.J.M.; Buuren, van J.C.L.; Mgana, S.

2014-01-01

Urban sanitation and solid waste sectors are under significant pressure in East Africa due to the lack of competent institutional capacity and the growth of the region’s urban population. This book presents and applies an original analytical approach to assess the existing socio-technical mixtures

Department of Energy Waste Information Network: Hazardous and mixed waste data management

International Nuclear Information System (INIS)

Fore, C.S.

1990-01-01

The Department of Energy (DOE) Waste Information Network (WIN) was developed through the efforts of the DOE Hazardous Waste Remedial Actions Program (HAZWRAP) Support Office (SO) to meet the programmatic information needs of the Director, Office of Environmental Restoration and Waste Management. WIN's key objective is to provide DOE Headquarters (HQ), DOE Operations Offices, and their contractors with an information management tool to support environmental restoration and waste management activities and to promote technology transfer across the DOE complex. WIN has evolved in various stages of growth driven by continued identification of user needs. The current system provides seven key features: technical information systems, bulletin boards, data file transfer, on-line conferencing, formal concurrence system, electronic messaging, and integrated spreadsheet/graphics. WIN is based on Digital Equipment Corporation;s (DEC) VAXcluster platform and is currently supporting nearly 1,000 users. An interactive menu system, DEC's ALL-IN-1 (1), provides easy access to all applications. WIN's many features are designed to provide the DOE waste management community with a repository of information management tools that are accessible, functional, and efficient. The type of tool required depends on the task to be performed, and WIN is equipped to serve many different needs. Each component of the system is evaluated for effectiveness for a particular purpose, ease of use, and quality of operation. The system is fully supported by project managers, systems analysts, and user assistance technicians to ensure subscribers of continued, uninterrupted service. 1 ref

Sustainable network of independent technical expertise for radioactive waste disposal

International Nuclear Information System (INIS)

Serres, Christophe; Rocher, Muriel; Lemy, Frank; Havlova, Vaclava; Mrskova, Adela; Heriard Dubreuil, Gilles

2014-01-01

Full text of publication follows: SITEX is a 24-month FP7 project led by IRSN and bringing together 15 organisations representing technical safety organisations (TSO) and safety authorities, as well as civil society outreach specialists involved in the 'regulatory' review process of geological disposal of radioactive waste. SITEX aims at establishing the conditions required for developing a sustainable network of experts from various horizons (authorities, TSO, academic organisations, civil society,...) capable of developing and coordinating the technical expertise that is required from the stakeholders in charge of delivering opinion, independently from the waste management organisations (WMO), on the safety of geological disposals. The SITEX programme of work is split into a set of six work packages that address technical and organisational issues allowing to propose a structure of the missions and operating mode of the future network. These issues relate on the one hand to the study of the potential for sharing and developing technical expertise practices amongst stakeholders, on the other hand on the ability to implement co-ordinated R and D programmes run by TSO in order to develop the scientific knowledge necessary to perform independent technical assessments. Two major perspectives are identified for the future of the SITEX network: its ability to foster co-operation between regulatory bodies, TSO, implementers and civil society with a view to enhancing common understanding of key safety issues and challenges and to identifying possible harmonisation of practices; the constitution of a scientific task force (mainly driven by TSO) for research definition and implementation at the European level allowing to improve the co-ordination of scientific programmes between TSO and developing its own skills and analytical tools, independently of the WMO. A comprehensive list of safety issues relevant to the development and implementation of a geological repository has

NRC regulations for disposal of high-level radioactive wastes in geologic repositories: technical criteria

International Nuclear Information System (INIS)

Martin, J.B.; Bell, M.J.; Regnier, E.P.

1983-01-01

The Nuclear Regulatory Commission is promulgating regulations specifying the technical criteria fo disposal of high-level radioactive wastes in geologic repositories. The proposed rule was published for public comment in July 1981. Public comments have been received and considered by the Commission staff. The Commission will soon approve and publish a revised final rule. While the final rule being considered by the Commission is fundamentally the same as the proposed rule, provisions have been added to permit flexibility in the application of numerical criteria, some detailed design requirements have been deleted, and other changes have been made in response to comments. The rule is consistent with the recently enacted Nuclear Waste Policy Act of 1982

Regional analysis of potential energy production from agricultural wastes: technical and economic study. Final report

Energy Technology Data Exchange (ETDEWEB)

Have, H

1981-01-01

The possibilities for utilization of agricultural wastes for energy production are analyzed in two Danish counties, Ringkoebing and Vestsjaelland, which have different agricultural production patterns. The quantitative analysis shows that the major waste products, surplus straw, waste wood and animal waste, in total with present technique can cover about 28% of the demand for heat energy (mostly space heating) in both counties. The potential coverage from straw, wood and animal waste is about 3, 3 and 22% in Ringkoebing and 18, 2 and 8% in Vestsjaelland respectively. A technical analysis indicates that direct combustion is the most favorable conversion method for straw and wood while biological conversion at present is best suited for animal waste. An economic analysis based on costs of collection, storage, transport and conversion of wastes and costs of corresponding oil and oil conversion were made. From a community point of view only straw and wood are found to be competitive to the expensive gas fuel oil when burned in automatically stoked furnaces. From a heating station point of view waste utilization is more attractive because of the sales tax on oil products. Here straw and wood are competitive fuels to both gas and heavy fuel oil in all the analyzed systems except from the small manually stoked furnaces. Animal waste seems to be competitive only when replacing gas fuel oil in medium size (500 kW) well utilized aerobic fermenters.

Biodegradation testing of TMI-2 EPICOR-II waste forms

International Nuclear Information System (INIS)

Rogers, R.D.; McConnell, J.W. Jr.

1988-06-01

ASTM biodegradation tests were conducted on waste forms containing high specific activity ion exchange resins from EPICOR-II prefilters. Those tests were part of a program to test waste forms in accordance with the NRC Branch Technical Position on Waste Form. Small waste forms were manufactured using two different solidification agents, Portland Type I-II cement and vinyl ester-styrene (VES). Ion exchange material was taken from two EPICOR-II prefilters; PF-7, which contained all organic material, and PF-20, which contained organic resins and a layer of inorganic zeolites. Test results showed that the VES waste forms supported microbial growth, while cement waste forms did not support that growth. Growth was also observed adjacent to some VES waste forms. Radiation levels found in the ion exchange resins used in this study were not found to inhibit microbial growth. The extent of degradation of the waste forms could not be determined using the ASTM tests specified by the NRC Branch Technical Position on Waste Form. As a result of this work, a different testing methodology is recommended, which would provide direct verification of waste form capabilities. That methodology would evaluate solidification materials without using the ASTM procedures or subsequent compression testing. The proposed tests would provide exposure to a wide range of microbial species, use appropriately sized specimens, provide for possible use of alternate carbon sources, and extend the test length. Degradation would be determined directly by measuring metabolic activity or specimen weight loss. 16 refs., 15 figs., 3 tabs

The WIPP research and development program: providing the technical basis for defense waste disposal

International Nuclear Information System (INIS)

Hunter, Th.O.

1983-01-01

The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

Requirements Development Issues for Advanced Life Support Systems: Solid Waste Management

Science.gov (United States)

Levri, Julie A.; Fisher, John W.; Alazraki, Michael P.; Hogan, John A.

2002-01-01

Long duration missions pose substantial new challenges for solid waste management in Advanced Life Support (ALS) systems. These possibly include storing large volumes of waste material in a safe manner, rendering wastes stable or sterilized for extended periods of time, and/or processing wastes for recovery of vital resources. This is further complicated because future missions remain ill-defined with respect to waste stream quantity, composition and generation schedule. Without definitive knowledge of this information, development of requirements is hampered. Additionally, even if waste streams were well characterized, other operational and processing needs require clarification (e.g. resource recovery requirements, planetary protection constraints). Therefore, the development of solid waste management (SWM) subsystem requirements for long duration space missions is an inherently uncertain, complex and iterative process. The intent of this paper is to address some of the difficulties in writing requirements for missions that are not completely defined. This paper discusses an approach and motivation for ALS SWM requirements development, the characteristics of effective requirements, and the presence of those characteristics in requirements that are developed for uncertain missions. Associated drivers for life support system technological capability are also presented. A general means of requirements forecasting is discussed, including successive modification of requirements and the need to consider requirements integration among subsystems.

Characterization of cement and bitumen waste forms containing simulated low-level waste incinerator ash

International Nuclear Information System (INIS)

Westsik, J.H. Jr.

1984-08-01

Incinerator ash from the combustion of general trash and ion exchange resins was immobilized in cement and bitumen. Tests were conducted on the resulting waste forms to provide a data base for the acceptability of actual low-level waste forms. The testing was done in accordance with the US Nuclear Regulatory Commission Technical Position on Waste Form. Bitumen had a measured compressive strength of 130 psi and a leachability index of 13 as measured with the ANS 16.1 leach test procedure. Cement demonstrated a compressive strength of 1400 psi and a leachability index of 7. Both waste forms easily exceed the minimum compressive strength of 50 psi and leachability index of 6 specified in the Technical Position. Irradiation to 10 8 Rad and exposure to 31 thermal cycles ranging from +60 0 ) to -30 0 C did not significantly impact these properties. Neither waste form supported bacterial or fungal growth as measured with ASTM G21 and G22 procedures. However, there is some indication of biodegradation due to co-metabolic processes. Concentration of organic complexants in leachates of the ash, cement and bitumen were too low to significantly affect the release of radionuclides from the waste forms. Neither bitumen nor cement containing incinerator ash caused any corrosion or degradation of potential container materials including steel, polyethylene and fiberglass. However, moist ash did cause corrosion of the steel

Technical data summary supporting the spent nuclear fuel environment impact statement, March 1994

International Nuclear Information System (INIS)

Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

1994-03-01

This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River Site input data evaluates five programmatic options (including open-quotes No Actionclose quotes) ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a forty year period (FY-35) when it is assumed that the material will be dispositioned from the SRS. The original issue of the report which was prepared under severe time constraints contained many simplifications and assumptions. Although the revisions have corrected some of the shortcomings of the original report, it is still highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. The data represents the best effort by a significant group of technical personnel familiar with nuclear materials processing, handling, and storage; but it is likely that careful scrutiny will reveal numerous discrepancies, inconsistencies and omissions. Nor does this report attempt to analyze every potential disposal pathway, but probably establishes the bounds for the most of the viable pathways. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios which were changed since the last revision. The decision to limit reprocessing to only SRS aluminum clad required a major alteration of the TDS. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an EIS, has been updated since the last revision, but not thoroughly completed

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

International Nuclear Information System (INIS)

1995-02-01

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation's allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered

Disposal of high-level radioactive wastes in the unsaturated zone: technical considerations and response to comments. Final report

International Nuclear Information System (INIS)

Hackbarth, C.J.; Nicholson, T.J.; Evans, D.D.

1985-10-01

On July 22, 1985, the US Nuclear Regulatory Commission (NRC) promulgated amendments to 10 CFR Part 60 concerning disposal of high-level radioactive waste (HLW) in geologic repositories in the unsaturated zone (50 FR 29641). This report contains a discussion of the principal technical issues considered by the NRC staff during the development of these amendments. It expands or revises certain technical discussions originally presented in draft NUREG-1046 (February 1984) based on public comment letters and an increasing understanding of the physical, geochemical, and hydrogeologic processes operative in unsaturated geologic media. The following issues related to disposal of HLW within the unsaturated zone are discussed: hydrogeologic properties and conditions, heat dissipation and temperature, geochemisty, retrievability, potential for exhumation of the radioactive waste by natural causes and by human intrusion, the effects of future climatic changes on the level of the regional water table, and transport of radionuclides in the gaseous state. The changes to 10 CFR Part 60 in definitions, siting criteria, and design criteria for the geologic repository operations area are discussed. Other criteria examined by the NRC staff but which were not changed in rule are the minimum 300-meter depth for waste emplacement, limitations on exploratory boreholes, backfill requirements, waste package design criteria, and provisions for ventilation

End-of-waste criteria for waste plastic for conversion. Technical proposals.

OpenAIRE

VILLANUEVA KRZYZANIAK Alejandro; EDER Peter

2014-01-01

This report is the JRC-IPTS contribution to the development of the end-of-waste criteria for waste plastic in accordance with Article 6 of Directive 2008/98/EC of the European Parliament and of the Council on waste (the Waste Framework Directive). This report includes a possible set of end-of-waste criteria and shows how the proposals were developed based on a comprehensive techno-economic analysis of the waste plastic production chain and an analysis of the economic, environmental and le...

Management of radioactive waste at the Oak Ridge National Laboratory: a technical review

International Nuclear Information System (INIS)

1985-01-01

This review was performed for the US Department of Energy by a panel of the Board on Radioactive Waste Management under the National Research Council's Commission on Physical Sciences, Mathematics, and Resources. In summary, ORNL's waste management practices have kept offsite doses low; some of the practices are temporary and improvised - they may not be as satisfactory in the future; reducing anticipated future releases will be difficult because the limited number of candidate waste disposal locations are characterized by topographic peculiarities; and a major ORNL accomplishment has been the demonstration that hydrofracture can be a successful method of disposal for at least low- and intermediate-level waste. The panel obtained its information over a 2-year period by examining a large body of technical literature, by making six visits to the Oak Ridge National Laboratory, and through briefings by representatives of government agencies and their subcontractors. Chapter 2 contains the charge to the panel. Chapters 3, 4, and 5 describe the site, the waste that is present, and the methods used to handle it. Chapters 6 through 10 treat the manner in which the performance of the waste-handling system is monitored, the criteria against which performance is assessed, the panel's assessment of performance, and consideration of alternative methods for future handling of radioactive waste. Chapter 11 contains a brief comparison of ORNL with other sites. The panel's principal conclusions and recommendations are summarized below and treated in detail in subsequent chapters. In general, the conclusions and recommendations considered by the panel to be the most important are provided first. 123 refs., 30 figs., 24 tabs

Low level tank waste disposal study

Energy Technology Data Exchange (ETDEWEB)

Mullally, J.A.

1994-09-29

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

Low level tank waste disposal study

International Nuclear Information System (INIS)

Mullally, J.A.

1994-01-01

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

Waste and Encapsulation Storage Facility (WESF) Essential and Support Drawing List

International Nuclear Information System (INIS)

SHANNON, W.R.

1999-01-01

Provides listing of Essential and Support Drawings for the Waste and Encapsulation Storage Facility. The drawings identified in this document will comprise the Waste Encapsulation and Storage Facility essential and support drawing list. This list will replace drawings identified as the ''WESF Essential and support drawing list''. Additionally, this document will follow the applicable requirements of HNF-PRO-242 Engineering Drawing Requirements'' and FSP-WESF-001, Section EN-1 ''Documenting Engineering Changes''. An essential drawing is defined as an engineering drawing identified by the facility staff as necessary to directly support the safe operation or maintenance of the facility. A support drawing is defined as a drawing identified by the facility staff that further describes the design details of structures, systems, or components shown on essential drawings or is frequently used by the support staff

Estimation of Exposure Doses for Several Scenarios of the Landfill Disposal of NORM Wastes

Energy Technology Data Exchange (ETDEWEB)

Jeong, Jong Tae; Ko, Nak Yul; Baik, Min Hoon [KAERI, Daejeon (Korea, Republic of); Yoon, Ki Hoon [Korea Institude of Nuclear Safety, Daejeon (Korea, Republic of)

2016-05-15

The Act on safety control of radioactive materials around living environment was promulgated to protect citizen's health and environment in 2013. According to this Act, the integrated plan for radiation protection and the necessary safety guides for treatment, reuse, and disposal of NORM wastes have to be made. And NORM wastes have to be disposed in landfill sites by reducing the concentration of radionuclide, and they should not be reutilized. In this study, we estimated exposure doses for several scenarios for NORM (Naturally Occurring Radioactive Materials) waste disposal into a reference landfill site to check the radiological safety. Also, we estimated the amount of NORM wastes for different activity levels of important radionuclides in wastes to be disposed into a landfill site based on the exposure dose limits to support the establishment of technical bases for safety guide. We estimated the amount of NORM wastes for different activity levels of wastes containing U series, Th series, and {sup 40}K based on the exposure dose limits. The results of this study can be used as technical bases to support the establishment of a guide for the safe management of NORM waste disposal.

Realization of a technical and economic referential of units of organic waste processing by methanization with and without biogas valorization. Study report

International Nuclear Information System (INIS)

2010-01-01

Based on a literature survey and on the analysis of results obtained in operating installations in different countries (Germany, Denmark, France, Netherlands, and Switzerland), this study concerns the methanization of different substrates: domestic wastes, sludge from sewage processing plants, industrial wastes and effluents, agricultural wastes and effluents. This synthetic report describes the current status of methanization in terms of regulatory framework (for renewable energies, and for waste management, digestion residues and compost valorization in Europe and in the studied countries), and in terms of actual production and variety of base products. It gives an overview of the available technical solutions, of the products they use, and of the associated investment costs. These techniques are: completely stirred tank reactor (SCTR), upflow anaerobic sludge blanket (UASB), internal circulation (IC), 'piston', batch, percolation, contact, fluidized bed, and anaerobic filter. It reports a synthesis of answers given to a questionnaire about technical and economic aspects

Waste and Encapsulation Storage Facility (WESF) Essential and Support Drawing List

International Nuclear Information System (INIS)

SHANNON, W.R.

1999-01-01

This supporting document provides a detailed list of the Essential and Support drawing for the Waste and Storage Encapsulation Facility. The drawings identified in this document will comprise the Waste Encapsulation and Storage Facility essential and support drawing list. This list will replace drawings identified as the ''WESF Essential and support drawing list''. Additionally, this document will follow the applicable requirements of HNF-PRO-242 Engineering Drawing Requirements'' and FSP-WESF-001, Section EN-1 ''Documenting Engineering Changes''. An essential drawing is defined as an engineering drawing identified by the facility staff as necessary to directly support the safe operation or maintenance of the facility. A support drawing is defined as a drawing identified by the facility staff that further describes the design details of structures, systems, or components shown on essential drawings or is frequently used by the support staff

Waste Management Policy in Tourism Area of Saensuk Municipality, Thailand

OpenAIRE

Wijaya, Andy Fefta; Kaewmanee, Pongsathon

2014-01-01

Saensuk Municipality is a famous tourism city in Thailand, especially Bangsaen beach. In supporting the tourism activity, it has waste managing method by using new generation administrator and technologies. However, the waste problem happened in Saensuk Municipality is included the human resource ability, technical facility, and the amount of waste. By using the qualitative descriptive method and doing a series of interview to selected informants, the researcher studied and analyzed the probl...

Game-based dynamic simulations supporting technical education and training

Directory of Open Access Journals (Sweden)

Tore Bjølseth

2006-04-01

Full Text Available Educational games may improve learning by taking advantage of the new knowledge and skills of today’s students obtained from extensive use of interactive games. This paper describes how interactive dynamic simulators of advanced technical systems and phenomena can be shaped and adapted as games and competitions supporting technical education and training. Some selected examples at different educational levels are shown, from vocational training to university level courses. The potential benefit and perceived learning effect of this approach is also described and underpinned from comprehensive user feedback.

Developing Capacities in Radioactive Waste Management

International Nuclear Information System (INIS)

Yusuf, Omar

2014-01-01

As the Agency’s main service-delivery mechanism, the IAEA’s technical cooperation (TC) programme plays a large part in supporting radioactive waste management around the world, helping to share information on the topic, and training personnel in the proper treatment and disposal of radioactive waste. The TC programme supports the development of policies and strategies, the assessment and upgrading (if necessary) of existing facilities, and the implementation of new management facilities, especially for near surface disposal. The programme also helps to develop competence in geological disposal for Member States operating nuclear power plants. This article presents just a few project examples to illustrate the scope of the programme

Plutonium Equivalent Inventory for Belowground Radioactive Waste at the Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

International Nuclear Information System (INIS)

French, Sean B.; Shuman, Robert

2012-01-01

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Many aspects of the management of this waste are conducted at Technical Area 54 (TA-54); Area G plays a key role in these management activities as the Laboratory's only disposal facility for low-level radioactive waste (LLW). Furthermore, Area G serves as a staging area for transuranic (TRU) waste that will be shipped to the Waste Isolation Pilot Plant for disposal. A portion of this TRU waste is retrievably stored in pits, trenches, and shafts. The radioactive waste disposed of or stored at Area G poses potential short- and long-term risks to workers at the disposal facility and to members of the public. These risks are directly proportional to the radionuclide inventories in the waste. The Area G performance assessment and composite analysis (LANL, 2008a) project long-term risks to members of the public; short-term risks to workers and members of the public, such as those posed by accidents, are addressed by the Area G Documented Safety Analysis (LANL, 2011a). The Documented Safety Analysis uses an inventory expressed in terms of plutonium-equivalent curies, referred to as the PE-Ci inventory, to estimate these risks. The Technical Safety Requirements for Technical Area 54, Area G (LANL, 2011b) establishes a belowground radioactive material limit that ensures the cumulative projected inventory authorized for the Area G site is not exceeded. The total belowground radioactive waste inventory limit established for Area G is 110,000 PE-Ci. The PE-Ci inventory is updated annually; this report presents the inventory prepared for 2011. The approach used to estimate the inventory is described in Section 2. The results of the analysis are presented in Section 3.

Functional specifications for a radioactive waste decision support system

International Nuclear Information System (INIS)

Westrom, G.B.; Kurrasch, E.R.; Carlton, R.E.; Vance, J.N.

1989-09-01

It is generally recognized that decisions relative to the treatment, handling, transportation and disposal of low-level wastes produced in nuclear power plants involve a complex array of many inter-related elements or considerations. Complex decision processes can be aided through the use of computer-based expert systems which are based on the knowledge of experts and the inferencing of that knowledge to provide advice to an end-user. To determine the feasibility of developing and applying an expert system in nuclear plant low level waste operations, a Functional Specification for a Radwaste Decision Support System (RDSS) was developed. All areas of radwaste management, from the point of waste generation to the disposition of the waste in the final disposal location were considered for inclusion within the scope of the RDSS. 27 figs., 8 tabs

SRNL PHASE 1 Assessment Of The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the

Preclosure analysis of conceptual waste package designs for a nuclear waste repository in tuff

International Nuclear Information System (INIS)

O'Neal, W.C.; Gregg, D.W.; Hockman, J.N.; Russell, E.W.; Stein, W.

1984-01-01

This report discusses the selection and analysis of conceptual waste package developed by the Nevada Nuclear Waste Storage Investigations (NNWSI) project for possible disposal of high-level nuclear waste at a candidate site at Yucca Mountain, Nevada. The design requirements that the waste package must conform to are listed, as are several desirable design considerations. Illustrations of the reference and alternative designs are shown. Four austenitic stainless steels (316L SS, 321 SS, 304L SS and Incoloy 825 high nickel alloy) have been selected for candidate canister/overpack materials, and 1020 carbon steel has been selected as the reference metal for the borehole liners. A summary of the results of technical and ecnonmic analyses supporting the selection of the conceptual waste package designs is included. Postclosure containment and release rates are not analyzed in this report

Role of technical and scientific support organization In Indonesian regulatory body

International Nuclear Information System (INIS)

Yusri Heni, N.A.; Zarkasih, A.S.; Liliana, Y.P.; Salman, S.

2007-01-01

Indonesian Nuclear Energy Regulatory Agency (BAPETEN) has the function in controlling the utility of nuclear energy through regulation, licensing and inspection, with the aim, interalia, to ensure the welfare, the security and the peace of people, to assure the safety and the health of workers and public, and the environmental protection, and to prevent diversion of purpose of the nuclear material utilization (Article 14 and 15 of Act no 10, 1997 on Nuclear Energy). The role and quality of technical and scientific expertise in supporting regulatory systems are importance increase the effectiveness and public confidence. The Center for Regulatory Assessment of Nuclear Installation and Nuclear Material and Center for Regulatory Assessment of Radiation Facilities and Radioactive Sources as part of BAPETEN organization has a function as technical and scientific support for regulatory systems. The purpose of this function is to provide technical and scientific basis for decisions and activities regarding nuclear and radiation safety during regulatory processes, such as in the developing and establishing regulation, technical verification for licensing, assessment of inspection funding and enforcement. In order to meet the quality and effectiveness of technical and scientific result activity, those two centers for regulatory assesment used internal and external technical experts and joint cooperation with universities, research institutes or laboratories. The development of technical and scientific strategic planning in enhancing nuclear and radiation safety is done by the following increasing of : Human resources and expertise by internal and external training or on the job training; number for computer code to perform safety analysis, capability and quality for review and assessment, national and international cooperation, etc. (author)

Branch technical position on the use of expert elicitation in the high-level radioactive waste program

International Nuclear Information System (INIS)

Kotra, J.P.; Lee, M.P.; Eisenberg, N.A.; DeWispelare, A.R.

1996-11-01

Should the site be found suitable, DOE will apply to the US Nuclear Regulatory Commission for permission to construct and then operate a proposed geologic repository for the disposal of spent nuclear fuel and other high-level radioactive waste at Yucca Mountain. In deciding whether to grant or deny DOE's license application for a geologic repository, NRC will closely examine the facts and expert judgment set forth in any potential DOE license application. NRC expects that subjective judgments of individual experts and, in some cases, groups of experts, will be used by DOE to interpret data obtained during site characterization and to address the many technical issues and inherent uncertainties associated with predicting the performance of a repository system for thousands of years. NRC has traditionally accepted, for review, expert judgment to evaluate and interpret the factual bases of license applications and is expected to give appropriate consideration to the judgments of DOE's experts regarding the geologic repository. Such consideration, however, envisions DOE using expert judgments to complement and supplement other sources of scientific and technical information, such as data collection, analyses, and experimentation. In this document, the NRC staff has set forth technical positions that: (1) provide general guidelines on those circumstances that may warrant the use of a formal process for obtaining the judgments of more than one expert (i.e., expert elicitation); and (2) describe acceptable procedures for conducting expert elicitation when formally elicited judgments are used to support a demonstration of compliance with NRC's geologic disposal regulation, currently set forth in 10 CFR Part 60. 76 refs

Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

Goyette, M.L.; Dolak, D.A.

1996-12-01

This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

Radioactive waste products 2002 (RADWAP 2002). Proceedings

International Nuclear Information System (INIS)

Odoj, R.; Baier, J.; Brennecke, P.; Kuehn, K.

2003-01-01

The 4 th International Seminar on Radioactive Waste Products was organised by the Forschungszentrum Juelich in co-operation with the Bundesamt fuer Strahlenschutz and the European Commission. On behalf of the Bundesamt, I would like to welcome all participants of this scientific-technical meeting. I very much appreciate the participation not only of numerous German scientists, engineers and technicians as well as governmental and industrial representatives, but would particularly express my gratitude for the participation of many colleagues from abroad. Radioactive waste management and disposal is a worldwide issue and international co-operation to support national programmes is therefore much appreciated. The international organisations provide, among other things, guidance to member countries on safe, economic and environmentally acceptable solutions for radioactive waste disposal. On a national basis respective programmes are developed, modified or successfully realized. Nevertheless, the challenge of radioactive waste management and disposal is no longer a scientific and technical exclusivity. The importance of ethical and social aspects, the dialogue with the public and transparency in decision-making processes increase more and more. Thus, when addressing safety-related key questions one needs to be as open as possible on scientific-technical aspects and to consider the involvement of the public requiring a clear, open-minded and transparent communication. (orig.)

IGNEOUS INTRUSION IMPACTS ON WASTE PACKAGES AND WASTE FORMS

International Nuclear Information System (INIS)

Bernot, P.

2004-01-01

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The models are based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. The models described in this report constitute the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of LA (BSC 2004 [DIRS:167796]) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2003 [DIRS: 166296]). The technical work plan was prepared in accordance with AP-2.27Q, Planning for Science Activities. Any deviations from the technical work plan are documented in the following sections as they occur. The TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model assessments: (1) Mechanical and thermal impacts of basalt magma intrusion on the invert, waste packages and waste forms of the intersected emplacement drifts of Zone 1. (2) Temperature and pressure trends of basaltic magma intrusion intersecting Zone 1 and their potential effects on waste packages and waste forms in Zone 2 emplacement drifts. (3) Deleterious volatile gases, exsolving from the intruded basalt magma and their potential effects on waste packages of Zone 2 emplacement drifts. (4) Post-intrusive physical

Technical support and management systems for nuclear power stations

International Nuclear Information System (INIS)

Oya, Tadashi; Abe, Norihiko

1990-01-01

Sophisticated automatic monitoring and control capabilities and computerized operation management are needed in nuclear power plants to boost plant safety and availability and to reduce operating costs. The article covers the areas of operation management and maintenance management within the larger category of operational administration. The concept of technical administration support-that is, the use of computerization to support the on-site technician's operations-is introduced. The article also suggests the direction of future development. (author)

TWRS privatization support waste characterization database development. Volume 2

International Nuclear Information System (INIS)

Brevick, C.H.

1995-11-01

This appendix contains the radionuclide and chemical analyte subset data tables. These data tables contain all of the validated waste characterization information collected for the TWRS Privatization Support Project

Technical Support Document for Version 3.4.0 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2007-09-14

COMcheck provides an optional way to demonstrate compliance with commercial and high-rise residential building energy codes. Commercial buildings include all use groups except single family and multifamily not over three stories in height. COMcheck was originally based on ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989) requirements and is intended for use with various codes based on Standard 90.1, including the Codification of ASHRAE/IES Standard 90.1-1989 (90.1-1989 Code) (ASHRAE 1989a, 1993b) and ASHRAE/IESNA Standard 90.1-1999 (Standard 90.1-1999). This includes jurisdictions that have adopted the 90.1-1989 Code, Standard 90.1-1989, Standard 90.1-1999, or their own code based on one of these. We view Standard 90.1-1989 and the 90.1-1989 Code as having equivalent technical content and have used both as source documents in developing COMcheck. This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards.

Technical Support Document for Version 3.9.1 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2012-09-01

COMcheck provides an optional way to demonstrate compliance with commercial and high-rise residential building energy codes. Commercial buildings include all use groups except single family and multifamily not over three stories in height. COMcheck was originally based on ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989) requirements and is intended for use with various codes based on Standard 90.1, including the Codification of ASHRAE/IES Standard 90.1-1989 (90.1-1989 Code) (ASHRAE 1989a, 1993b) and ASHRAE/IESNA Standard 90.1-1999 (Standard 90.1-1999). This includes jurisdictions that have adopted the 90.1-1989 Code, Standard 90.1-1989, Standard 90.1-1999, or their own code based on one of these. We view Standard 90.1-1989 and the 90.1-1989 Code as having equivalent technical content and have used both as source documents in developing COMcheck. This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards. Beginning with COMcheck version 3.8.0, support for 90.1-1989, 90.1-1999, and the 1998 IECC and version 3.9.0 support for 2000 and 2001 IECC are no longer included, but those sections remain in this document for reference purposes.

Waste transmutation and public acceptance

International Nuclear Information System (INIS)

Pigford, T.H.

1991-01-01

The concept of transmuting radioactive wastes with reactors or accelerators is appealing. It has the potential of simplifying or eliminating problems of disposing of nuclear waste. The transmutation concept has been renewed vigorously at a time when national projects to dispose of high-level and transuranic waste are seriously delayed. In this period of tightening federal funds and program curtailments, skilled technical staffs are available at US Department of Energy (DOE) national laboratories and contractors to work on waste transmutation. If the claims of transmutation can be shown to be realistic, economically feasible, and capable of being implemented within the US institutional infrastructure, public acceptance of nuclear waste disposal may be enhanced. If the claims for transmutation are not substantiated, however, there will result a serious loss of credibility and an unjust exacerbation of public concerns about nuclear waste. The paper discusses the following topics: how public acceptance is achieved; the technical community and waste disposal; transmutation and technical communication; transmutation issues; technical fixes and public perception

Design of Technical Support System for Retail Company Based on Cloud

Directory of Open Access Journals (Sweden)

Shao Ping

2017-01-01

Full Text Available With the retail side of the market in China, the sale of electricity companies as a new source of power retail, they participate in the electricity market business. National and local governments subsequently introduced the corresponding policies and rules, the technical support system becomes one of the necessary conditions for the access of the retail company. Retail electricity companies have started the system construction, but has not yet formed a standardized, complete architecture. This paper analyzes the business and data interaction requirements of retail electricity companies, and then designs the functional architecture based on basic application, advanced application and value-added application, and the technical architecture based on “cloud”. On this basis, the paper discusses the selection of private cloud, public cloud and mixed cloud model, and the rationalization suggestion of system construction. Which can provide reference for the construction of the technical support system of the domestic retail enterprises.

An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

International Nuclear Information System (INIS)

Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

2013-01-01

Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

Knowledge-Centric Technical Support Organization (TSO) Using Process Oriented Knowledge Management Approach

International Nuclear Information System (INIS)

Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Mohd Dzul Aiman Aslan

2014-01-01

In the United States of America, Process Oriented Knowledge Management (POKM) Model has been successfully implemented in most of Nuclear Power Plants. This approach has been introduced in Nuclear Knowledge Management program by the IAEA since 2011. Malaysia has involved in the IAEA Coordinated Research Project (CRP) focusing the approach started in 2011. The main objective for Malaysian participation of this project is to support readiness in terms of nuclear technical knowledge by Technical Support Organization (TSO) for Nuclear Power Program. This project has focused on several nuclear technical areas which consist of Public Information (PI), Radiological Impact Assessment (RIA), Nuclear Reactor Technology (NRT), Plant and Prototype Development (PDC) and nuclear knowledge management. This paper articulates the detail POKM approach and project experience in implementing the approach at organizational level. (author)

Technical information report: Plasma melter operation, reliability, and maintenance analysis

International Nuclear Information System (INIS)

Hendrickson, D.W.

1995-01-01

This document provides a technical report of operability, reliability, and maintenance of a plasma melter for low-level waste vitrification, in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. A process description is provided that minimizes maintenance and downtime and includes material and energy balances, equipment sizes and arrangement, startup/operation/maintence/shutdown cycle descriptions, and basis for scale-up to a 200 metric ton/day production facility. Operational requirements are provided including utilities, feeds, labor, and maintenance. Equipment reliability estimates and maintenance requirements are provided which includes a list of failure modes, responses, and consequences

Nuclear Waste Management Decision-Making Support with MCDA

Directory of Open Access Journals (Sweden)