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Waste Emplacement/Retrieval System Description Document
The Waste Emplacement/Retrieval System transports Waste Packages (WPs) from the Waste Handling Building (WHB) to the subsurface area of emplacement, and emplaces the WPs once there. The Waste Emplacement/Retrieval System also, if necessary, removes some or all of the WPs from the underground and transports them to the surface. Lastly, the system is designed to remediate abnormal events involving the portions of the system supporting emplacement or retrieval. During emplacement operations, the system operates on the surface between the WHB and North Portal, and in the subsurface in the North Ramp, access mains, and emplacement drifts. During retrieval or abnormal conditions, the operations areas may also extend to a surface retrieval storage site and South Portal on the surface, and the South Ramp in the subsurface. A typical transport and emplacement operation involves the following sequence of events. A WP is loaded into a WP transporter at the WHB, and coupled to a pair of transport locomotives. The locomotives transport the WP from the WHB, down the North Ramp, and to the entrance of an emplacement drift. Once docked at the entrance of the emplacement drift, the WP is moved outside of the WP transporter, and engaged by a WP …
Date:
July 25, 2001
Creator:
Loros, Eric
Object Type:
Report
System:
The UNT Digital Library
Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)
This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.
Date:
July 29, 1996
Creator:
Maddox, B.S., Westinghouse Hanford
Object Type:
Report
System:
The UNT Digital Library
Waste feed delivery environmental permits and approvals plan
This document describes the range of environmental actions, including required permits and other agency approvals, that may affect waste feed delivery (WFD) activities in the Hanford Site`s Tank Waste Remediation System (TWRS). This plan expands on the summary level information in the Tank Waste Remediation System Environmental Program Plan (HNF 1773) to address requirements that are most pertinent to WFD. This plan outlines alternative approaches to satisfying applicable environmental standards, and describes selected strategies for acquiring permits and other approvals needed for WFD to proceed. Appendices at the end of this plan provide preliminary cost and schedule estimates for implementing the selected strategies. The rest of this section summarizes the scope of WFD activities, including important TWRS operating information, and describes in more detail the objectives, structure, and content of this plan.
Date:
July 6, 1998
Creator:
Papp, I.G.
Object Type:
Report
System:
The UNT Digital Library
Waste form characteristics report, revision 1.3
This Waste Form Characteristics Report (WFCR) update, Version 1.3, incorporates substantial additions and changes to following 10 sections of the WFCR: 2.1.3.1 Cladding Degradation; 2.1.3.2 UO2 Oxidation in Fuel; 2.1.3.5 Dissolution Release from UO{sub 2}; 2.2.1.5 Fracture /Fragmentation Studies of Glass; 2.2.2.2 Dissolution Radionuclide Release from Glass; 2.2.2.3 Soluble-Precipitated/Colloidal Species from Glass; 3.2.2 Spent-Fuel Oxidation Models; 3.4.2 Spent-Fuel Dissolution Models; 3.5.1 Glass Dissolution Experimental Parameters; and 3.5.2 Glass Dissolution Models.
Date:
July 1, 1998
Creator:
Leider, H. R. & Stout, R. B.
Object Type:
Report
System:
The UNT Digital Library
Waste, Fraud, and Abuse in Agency Travel Card Programs
This report begins by discussing the structure of agency travel card programs, and then discusses weaknesses in agency controls that have contributed to waste, fraud, and abuse. It then examines travel card legislation introduced or enacted in the 111th Congress, and concludes with observations on the information available to Congress for oversight of agency travel card programs.
Date:
July 20, 2009
Creator:
Hatch, Garrett
Object Type:
Report
System:
The UNT Digital Library
Waste gas combustion in a Hanford radioactive waste tank
It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), …
Date:
July 1, 1994
Creator:
Travis, J. R.; Fujita, R. K. & Spore, J. W.
Object Type:
Article
System:
The UNT Digital Library
WASTE HANDLING FACILITIES RECOVERY ANALYSIS
None
Date:
July 3, 1997
Creator:
TOME, R.
Object Type:
Report
System:
The UNT Digital Library
Waste Isolation Pilot Plant Groundwater Protection Management Program Plan
The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP …
Date:
July 1, 2005
Creator:
Services, Washington Regulatory and Environmental
Object Type:
Report
System:
The UNT Digital Library
Waste Isolation Safety Assessment Program. Technical progress report for FY-1978
Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)
Date:
July 1, 1979
Creator:
Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R. et al.
Object Type:
Report
System:
The UNT Digital Library
Waste management aspects of decontamination and decommissioning (D&D) projects
History shows that waste management concepts have generally been overlooked during the planning stages of most projects and experiments. This is resulting,in the generation of vast amounts of waste during the clean up or D&D of these facilities. Managers are not only being frustrated in their waste minimization efforts (a relatively new concept) but are also facing the prospect of not being able to dispose of the waste materials at all. At the least, managers are having to budget extraordinary amounts of time, money, and effort in defending their positions that the waste materials are not only humanly and environmentally safe, but that the waste materials are in fact what management says they are. The following discussion will attempt to provide some guidance to D&D managers to help them avoid many of the common pitfalls associated with the ultimate disposal of the materials generated during these projects.
Date:
July 1, 1993
Creator:
Becker, B. D.
Object Type:
Article
System:
The UNT Digital Library
Waste Management Facilities Cost Information report for Greater-Than-Class C and DOE equivalent special case waste
This Waste Management Facility Cost Information (WMFCI) report for Greater-Than-Class C low-level waste (GTCC LLW) and DOE equivalent special case waste contains preconceptual designs and planning level life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities needed for management of GTCC LLW and DOE equivalent waste. The report contains information on 16 facilities (referred to as cost modules). These facilities are treatment facility front-end and back-end support functions (administration support, and receiving, preparation, and shipping cost modules); seven treatment concepts (incineration, metal melting, shredding/compaction, solidification, vitrification, metal sizing and decontamination, and wet/air oxidation cost modules); two storage concepts (enclosed vault and silo); disposal facility front-end functions (disposal receiving and inspection cost module); and four disposal concepts (shallow-land, engineered shallow-land, intermediate depth, and deep geological cost modules). Data in this report allow the user to develop PLCC estimates for various waste management options. A procedure to guide the U.S. Department of Energy (DOE) and its contractor personnel in the use of estimating data is also included in this report.
Date:
July 1, 1993
Creator:
Feizollahi, F. & Shropshire, D.
Object Type:
Report
System:
The UNT Digital Library
Waste management plan for inactive LLLW tanks 3001-B, 3004-B, 3013, and T-30 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program
This Project Waste Management Plan identifies the waste that is expected to be generated in connection with the removal and disposition of inactive liquid low-level radioactive waste tanks 3001-B, 3004-B, and T-30, and grouting of tank 3013 at the Oak Ridge National Laboratory and the isolation of these tanks` associated piping systems. The plan also identifies the organization, responsibilities, and administrative controls that will be followed to ensure proper handling of the waste.
Date:
July 1, 1995
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Waste Management Program. Technical progress report, October-December 1982
This quarterly report provides current 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, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.
Date:
July 1, 1983
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Waste minimization and pollution prevention awareness plan. Revision 1
The purpose of this plan is to document Lawrence Livermore National Laboratory (LLNL) projections for present and future waste minimization and pollution prevention. The plan specifies those activities and methods that are or will be used to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) requirements. This Waste Minimization and Pollution Prevention Awareness Plan provides an overview of projected activities from FY 1994 through FY 1999. The plans are broken into site-wide and problem-specific activities. All directorates at LLNL have had an opportunity to contribute input, estimate budgets, and review the plan. In addition to the above, this plan records LLNL`s goals for pollution prevention, regulatory drivers for those activities, assumptions on which the cost estimates are based, analyses of the strengths of the projects, and the barriers to increasing pollution prevention activities.
Date:
July 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Waste minimization and pollution prevention in D&D operations at the Argonne National Laboratory-East site
Argonne National Laboratory (ANL) is implementing waste minimization and pollution prevention activities into its conduct of decontamination and decommissioning (D&D) projects. Many of these activities are rather straight forward and simple approaches, yet they are often overlooked and not implemented as often as they should or could be. Specific activities involving recycling and reuse of materials and structures, which have proven useful in lowering decommissioning and disposal costs on D&D projects at ANL are presented.
Date:
July 1, 1996
Creator:
Boing, L. E.; Coffey, M. J.; Ditch, R. W.; Fellhauer, C. R. & Rose, R. W.
Object Type:
Article
System:
The UNT Digital Library
Waste minimization for commercial radioactive materials users generating low-level radioactive waste
The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.
Date:
July 1, 1991
Creator:
Fischer, D. K.; Gitt, M.; Williams, G. A.; Branch, S. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Otis, M. D.; McKenzie-Carter, M. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1
The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.
Date:
July 1, 1991
Creator:
Fischer, D. K.; Gitt, M.; Williams, G. A.; Branch, S.; Otis, M. D.; McKenzie-Carter, M. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Waste monitoring system for effluents
The waste monitoring system in use at Los Alamos National Laboratory`s Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system.
Date:
July 1, 1995
Creator:
Macdonald, J. M.; Gomez, B.; Trujillo, L.; Malcom, J. E.; Nekimken, H.; Pope, N. et al.
Object Type:
Report
System:
The UNT Digital Library
Waste Package Component Design Methodology Report
This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in …
Date:
July 12, 2004
Creator:
Mecham, D. C.
Object Type:
Report
System:
The UNT Digital Library
Waste Package Program
This was a progress report on the research program of waste packages at the University of Nevada, Las Vegas. The report has the overviews of what the program has done from January 1991 to June 1991, such as task assignments for personnel, equipment acquisitions, and staff meetings and travels on behalf of the project. Also, included was an abstract on the structural analysis of the waste package container design. (MB)
Date:
July 21, 1991
Creator:
Culbreth, W. & Ladkany, S.
Object Type:
Report
System:
The UNT Digital Library
Waste Package Program. Progress report, January 1991--June 1991
This was a progress report on the research program of waste packages at the University of Nevada, Las Vegas. The report has the overviews of what the program has done from January 1991 to June 1991, such as task assignments for personnel, equipment acquisitions, and staff meetings and travels on behalf of the project. Also, included was an abstract on the structural analysis of the waste package container design. (MB)
Date:
July 21, 1991
Creator:
Culbreth, W. & Ladkany, S.
Object Type:
Report
System:
The UNT Digital Library
Waste package project quarterly report, April 1, 1995--June 30, 1995
Research activities spanned multidisciplinary areas: structural and stress analysis of the container including nonlinear yield and damage assessment and structural stability studies of the dynamic behavior of the steel multipurpose container under normal and accidental handling conditions; nuclear fission criticality studies in the canisters; investigation of novel canister design concepts and corrosion studies; heat transfer studies of the waste canisters and in adjacent rock drifts; fluid flow in porous media and radionuclide transport in near field rock; stresses and stability of the rock formations resulting from thermal loading of fuel elements and multi-tunnel concept being analyzed; faulted rock tunnel model; and three link steel robot for remote handling of high level nuclear waste.
Date:
July 20, 1995
Creator:
Ladkany, S.G.
Object Type:
Report
System:
The UNT Digital Library
Waste Preparation and Transport Chemistry: Results of the FY 2002 Studies
The initial step in the remediation of nuclear waste stored at Hanford and the Savannah River Site (SRS) involves the retrieval and transfer of the waste to another tank or to a treatment facility. The retrieved waste can range from a filtered supernatant to a slurry. Nearly all of the recent solid formation problems encountered during waste transfers and subsequent treatment steps have involved decanted or filtered supernatants. Problems with slurry transfers have not yet surfaced, because tank farm operations at Hanford and the SRS have focused primarily on supernatant transfers and treatment. For example, the interim stabilization program at Hanford continues to reduce the level of supernatants and interstitial liquids in its single-shell tanks through saltwell pumping of filtered liquid. In addition, at present, the cross-site transfer lines at Hanford can be used only to transfer liquids. Another reason for fewer problems with slurry transfers involves the additions of large quantities of dilution water prior to the transfer. When the waste is transferred, a drop in temperature is expected because most transfer lines are not heated. However, the dilution water reduces or eliminates solid formation caused by this temperature drop. In sharp contrast, decanted or filtered supernatants are near …
Date:
July 10, 2003
Creator:
Hunt, R.D.
Object Type:
Report
System:
The UNT Digital Library
Waste processing air cleaning
Waste processing and preparing waste to support waste processing relies heavily on ventilation. Ventilation is used at the Hanford Site on the waste storage tanks to provide confinement, cooling, and removal of flammable gases.
Date:
July 27, 1998
Creator:
Kriskovich, J. R.
Object Type:
Article
System:
The UNT Digital Library