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Sample records for disposal facility designs

  1. Conceptual design report for Central Waste Disposal Facility

    SciTech Connect

    Not Available

    1984-03-30

    The permanent facilities are defined, and cost estimates are provided for the disposal of Low-Level Radioactive Wastes (LLW) at the Central Waste Disposal Facility (CWDF). The waste designated for the Central Waste Disposal Facility will be generated by the Y-12 Plant, the Oak Ridge Gaseous Diffusion Plant, and the Oak Ridge National Laboratory. The facility will be operated by ORNL for the Office of Defense Waste and By-Products Management of the Deparment of Energy. The CWDF will be located on the Department of Energy's Oak Ridge Reservation, west of Highway 95 and south of Bear Creek Road. The body of this Conceptual Design Report (CDR) describes the permanent facilities required for the operation of the CWDF. Initial facilities, trenches, and minimal operating equipment will be provided in earlier projects. The disposal of LLW will be by shallow land burial in engineered trenches. DOE Order 5820 was used as the performance standard for the proper disposal of radioactive waste. The permanent facilities are intended for beneficial occupancy during the first quarter of fiscal year 1989. 3 references, 9 figures, 7 tables.

  2. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, S. L.

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  3. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    SciTech Connect

    Austad, Stephanie Lee

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  4. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  5. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  6. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2010-05-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  7. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2010-02-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  8. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    SciTech Connect

    NSTec Environmental Management

    2009-01-31

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

  9. Technical and design update in the AUBE French low-level radioactive waste disposal facility

    SciTech Connect

    Marque, Y.

    1989-01-01

    Long-term industrial management of radioactive waste in France is carried out by the Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA). ANDRA is in charge of design, siting, construction, and operation of disposal centers. The solution selected in France for the disposal of low- and medium-level, short-lived radioactive waste is near-surface disposal in the earth using the principle of multiple barriers, in accordance with national safety rules and regulations, and based on operating experience from the Centre de Stockage de la Manche. Since the center's start-up in 1969, 400,000 m{sup 3} of waste have been disposed of. The French national program for waste management is proceeding with the construction of a second near-surface disposal, which is expected to be operational in 1991. It is located in the department of AUBE (from which its name derives), 100 miles southeast of Paris. The paper describes the criteria for siting and design of the AUBE disposal facility, design of the AUBE facility disposal module, and comparison with North Carolina and Pennsylvania disposal facility designs.

  10. The design and licensing status of the Central Interstate Compact facility: An above-grade LLRW disposal facility

    SciTech Connect

    Gunning, J.E.; Sabbe, M.A.; Schulman, R.F.; DeOld, J.H.

    1997-07-01

    The Central Interstate Compact (CIC) low-level radioactive waste (LLRW) disposal facility being developed near Butte, Nebraska, is scheduled to be the first operational commercial above-grade LLRW disposal facility in the United States. The facility will dispose of LLRW generated by nuclear power plants, industrial facilities, hospitals, and universities from the CIC member states of Nebraska, Kansas, Oklahoma, Arkansas, and Louisiana. The CIC Commission has contracted with US Ecology and its prime subcontractor, Bechtel National Inc., to develop this LLRW disposal facility. The facility is being sited, designed, constructed, operated, closed, and monitored in accordance with Nebraska Department of Environmental Quality Title 194, which is similar to 10 CFR 61 but has some additional requirements that are specific to the State of Nebraska. One of these is that Nebraska regulations specifically exclude the use of traditional shallow-land burial as practiced prior to 1979. The facility will use above-grade earth-mounded concrete structures for disposal of the LLRW. An environmental report (ER) has been prepared that follows the guidance contained in U.S. Nuclear Regulatory Commission Regulatory Guide 4.18. A Safety Analysis Report (SAR) has been prepared that conforms to the guidance contained in NUREG 1199, Both the SAR and the ER were submitted in July 1990. Present plans calls for the facility to be operational approximately 2 years after receipt of the license.

  11. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    SciTech Connect

    Carter, R.L. Jr.

    1994-11-07

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS).

  12. Durability of a reinforced concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2012-01-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on a reinforced concrete specifically designed for this purpose, to predict the service life of the intermediate level radioactive waste disposal facility from data obtained with several techniques. Results obtained with corrosion sensors embedded in a concrete prototype are also included. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

  13. The design methodology and the safety concept of the surface disposal facility for the Belgian category A waste at Dessel

    SciTech Connect

    Wacquier, William; Bastiaens, Wim; Cool, Wim

    2013-07-01

    The paper describes the design methodology that ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials, has developed and applied in the framework of the surface disposal facility for category A waste, i.e. solid conditioned low level radioactive waste that contains a limited amount of long lived radionuclides, at Dessel. The proposed disposal facility supporting the submitted construction and operation license application [1, 2] is also presented. (authors)

  14. Cost estimates and economic evaluations for conceptual LLRW disposal facility designs

    SciTech Connect

    Baird, R.D.; Chau, N.; Breeds, C.D.

    1995-12-31

    Total life-cycle costs were estimated in support of the New York LLRW Siting Commission`s project to select a disposal method from four near-surface LLRW disposal methods (namely, uncovered above-grade vaults, covered above-grade vaults, below-grade vaults, and augered holes) and two mined methods (namely, vertical shaft mines and drift mines). Conceptual designs for the disposal methods were prepared and used as the basis for the cost estimates. Typical economic performance of each disposal method was assessed. Life-cycle costs expressed in 1994 dollars ranged from $ 1,100 million (for below-grade vaults and both mined disposal methods) to $2,000 million (for augered holes). Present values ranged from $620 million (for below-grade vaults) to $ 1,100 million (for augered holes).

  15. Integrated Disposal Facility Risk Assessment

    SciTech Connect

    MANN, F. M.

    2003-06-03

    An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.

  16. Design, construction and management of tailings storage facilities for surface disposal in China: case studies of failures.

    PubMed

    Wei, Zuoan; Yin, Guangzhi; Wang, J G; Wan, Ling; Li, Guangzhi

    2013-01-01

    Rapid development of China's economy demands for more mineral resources. At the same time, a vast quantity of mine tailings, as the waste byproduct of mining and mineral processing, is being produced in huge proportions. Tailings impoundments play an important role in the practical surface disposal of these large quantities of mining waste. Historically, tailings were relatively small in quantity and had no commercial value, thus little attention was paid to their disposal. The tailings were preferably discharged near the mines and few tailings storage facilities were constructed in mainland China. This situation has significantly changed since 2000, because the Chinese economy is growing rapidly and Chinese regulations and legislation require that tailings disposal systems must be ready before the mining operation begins. Consequently, data up to 2008 shows that more than 12 000 tailings storage facilities have been built in China. This paper reviews the history of tailings disposal in China, discusses three cases of tailings dam failures and explores failure mechanisms, and the procedures commonly used in China for planning, design, construction and management of tailings impoundments. This paper also discusses the current situation, shortcomings and key weaknesses, as well as future development trends for tailings storage facilities in China.

  17. Disposal facility data for the interim performance

    SciTech Connect

    Eiholzer, C.R.

    1995-05-15

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 {times} 2 {times} 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs.

  18. The status of LILW disposal facility construction in Korea

    SciTech Connect

    Kim, Min-Seok; Chung, Myung-Sub; Park, Kyu-Wan

    2013-07-01

    In this paper, we discuss the experiences during the construction of the first LILW disposal facility in South Korea. In December 2005, the South Korean Government designated Gyeongju-city as a host city of Low- and Intermediate-Level Radioactive Waste(LILW) disposal site through local referendums held in regions whose local governments had applied to host disposal facility in accordance with the site selection procedures. The LILW disposal facility is being constructed in Bongilri, Yangbuk-myeon, Gyeongju. The official name of the disposal facility is called 'Wolsong Low and Intermediate Level Radioactive Waste Disposal Center (LILW Disposal Center)'. It can dispose of 800,000 drums of radioactive wastes in a site of 2,100,000 square meters. At the first stage, LILW repository of underground silo type with disposal capacity of 100,000 drums is under construction expected to be completed by June of 2014. The Wolsong Low and Intermediate Level Radioactive Waste Disposal Center consists of surface facilities and underground facilities. The surface facilities include a reception and inspection facility, an interim storage facility, a radioactive waste treatment building, and supporting facilities such as main control center, equipment and maintenance shop. The underground facilities consist of a construction tunnel for transport of construction equipment and materials, an operation tunnel for transport of radioactive waste, an entrance shaft for workers, and six silos for final disposal of radioactive waste. As of Dec. 2012, the overall project progress rate is 93.8%. (authors)

  19. Corrosion behaviour of steel rebars embedded in a concrete designed for the construction of an intermediate-level radioactive waste disposal facility

    NASA Astrophysics Data System (ADS)

    Duffó, G. S.; Arva, E. A.; Schulz, F. M.; Vazquez, D. R.

    2013-07-01

    The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on an instrumented reinforced concrete prototype specifically designed for this purpose, to study the behaviour of an intermediate level radioactive waste disposal facility from the rebar corrosion point of view. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

  20. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    SciTech Connect

    Birk, S.M.

    1997-10-01

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country`s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today`s standards. This report summarizes each site`s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US.

  1. HANDBOOK: GUIDE TO TECHNICAL RESOURCES FOR THE DESIGN OF LAND DISPOSAL FACILITIES

    EPA Science Inventory

    This Handbook facilitates the preparation and processing of land disposal permit applications. It directs the regulated community and the regulators to the appropriate EPA technical resource documents, as they prepare or review permits required under PL 480 (RCRA). Topics discuss...

  2. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for...

  3. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for...

  4. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for...

  5. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Disposal site design for land disposal. 61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.51 Disposal site design for...

  6. Project W-049H disposal facility test report

    SciTech Connect

    Buckles, D.I.

    1995-01-01

    The purpose of this Acceptance Test Report (ATR) for the Project W-049H, Treated Effluent Disposal Facility, is to verify that the equipment installed in the Disposal Facility has been installed in accordance with the design documents and function as required by the project criteria.

  7. Undrained shear strength of partially saturated combined coal refuse. First annual report: Strength and consolidation characteristics of coal refuse for design and construction of disposal facilities

    SciTech Connect

    Huang, Y.H.; Li, J.

    1986-09-01

    This report summarizes the results of a study on the undrained shear strength of partially saturated combined refuse. The study is part of a research project entitled 'Strength and Consolidation Characteristics of Coal Refuse for Design and Construction of Disposal Facilities supported by the Office of Surface Mining, Department of the Interior. Information presented in the report will be used for the design and construction of disposal facilities. Coal refuse, the waste product from coal washing, is separated in the coal preparation plant into two fractions (coarse and fine). The fine refuse, in the form of either a slurry or a filter cake, is unstable and difficult to handle.

  8. Lessons Learned from Radioactive Waste Storage and Disposal Facilities

    SciTech Connect

    Esh, David W.; Bradford, Anna H.

    2008-01-15

    The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed

  9. Oil field waste disposal costs at commercial disposal facilities

    SciTech Connect

    Veil, J.A.

    1997-10-01

    The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

  10. 200 Area treated effluent disposal facility operational test report

    SciTech Connect

    Crane, A.F.

    1995-03-01

    This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met.

  11. RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report

    SciTech Connect

    Annette L. Schafer

    2012-06-01

    A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: • Department of Energy Order 435.1, “Radioactive Waste Management,” requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan • Environmental assessment supporting the National Environmental Policy Act • Nuclear safety • Safeguards and security • Emplacement operations • Requirements for commissioning • General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

  12. Strength and consolidation characteristics of coal refuse for design and construction of disposal facilities: Applications of research findings. Final report

    SciTech Connect

    Huang, Y.H.

    1987-08-01

    The use of coal refuse properties for the short-term stability analysis of disposal facilities is illustrated in the report. Three types of disposal facilities are considered: waste embankments constructed of combined or fine refuse, refuse dams constructed by upstream method, and sandwich construction by placing coarse and fine refuse in alternate layers. Detailed procedures are presented to determine the factor of safety at the end of construction using the REAME computer program developed at the University of Kentucky. The results of analysis show that limiting the maximum moisture content of combined or fine refuse in waste embankments and keeping the construction of refuse dams at a slower pace are very important for short-term stability. Due to the granular nature of coarse and fine refuse, the use of sandwich construction appears to be an efficient and economical disposal method. To compare the properties of coal refuse from the Western Coal Field with those from the Eastern Coal Field reported previously, test results on combined and fine refuse taken from two sites in Colorado are presented.

  13. Definitive design report: Design report project W-025, Radioactive Mixed Waste (RMW) Land Disposal Facility NON-DRAG-OFF. Revision 1, Volume 1 and 2

    SciTech Connect

    Roscha, V.

    1994-11-29

    The purpose of this report is to describe the definitive design of the Radioactive Mixed Waste (RMW) Non-Drag-Off disposal facility, Project W-025. This report presents a n of the major landfill design features and a discussion of how each of the criteria is addressed in the design. The appendices include laboratory test results, design drawings, and individual analyses that were conducted in support of the design. Revision 1 of this document incorporates design changes resulting from an increase in the required operating life of the W-025 landfill from 2 to 20 years. The rationale for these design changes is described in Golder Associates Inc. 1991a. These changes include (1) adding a 1.5-foot-thick layer of compacted admix directory-under the primary FML on the floor of the landfill to mitigate the effects of possible stress cracking in the primary flexible membrane liner (FML), and (2) increasing the operations layer thickness from two to three feet over the entire landfill area, to provide additional protection for the secondary admix layer against mechanical damage and the effects of freezing and desiccation. The design of the W-025 Landfill has also been modified in response to the results of the EPA Method 9090 chemical compatibility testing program (Golder Associates Inc. 1991b and 1991c), which was completed after the original design was prepared. This program consisted of testing geosynthetic materials and soil/bentonite admix with synthetic leachate having the composition expected during the life of the W-025 Landfill., The results of this program indicated that the polyester geotextile originally specified for the landfill might be susceptible to deterioration. On this basis, polypropylene geotextiles were substituted as a more chemically-resistant alternative. In addition, the percentage of bentonite in the admix was increased to provide sufficiently low permeability to the expected leachate.

  14. Developing operating procedures for a low-level radioactive waste disposal facility

    SciTech Connect

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  15. Acceptance test procedure: RMW Land Disposal Facility Project W-025

    SciTech Connect

    Roscha, V.

    1994-12-12

    This ATP establishes field testing procedures to demonstrate that the electrical/instrumentation system functions as intended by design for the Radioactive Mixed Waste Land Disposal Facility. Procedures are outlined for the field testing of the following: electrical heat trace system; transducers and meter/controllers; pumps; leachate storage tank; and building power and lighting.

  16. Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities

    SciTech Connect

    Batandjieva, B.; Torres-Vidal, C.

    2002-02-26

    The International Atomic Energy Agency (IAEA) Coordinated research program ''Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities'' (ISAM) has developed improved safety assessment methodology for near surface disposal facilities. The program has been underway for three years and has included around 75 active participants from 40 countries. It has also provided examples for application to three safety cases--vault, Radon type and borehole radioactive waste disposal facilities. The program has served as an excellent forum for exchange of information and good practices on safety assessment approaches and methodologies used worldwide. It also provided an opportunity for reaching broad consensus on the safety assessment methodologies to be applied to near surface low and intermediate level waste repositories. The methodology has found widespread acceptance and the need for its application on real waste disposal facilities has been clearly identified. The ISAM was finalized by the end of 2000, working material documents are available and an IAEA report will be published in 2002 summarizing the work performed during the three years of the program. The outcome of the ISAM program provides a sound basis for moving forward to a new IAEA program, which will focus on practical application of the safety assessment methodologies to different purposes, such as licensing radioactive waste repositories, development of design concepts, upgrading existing facilities, reassessment of operating repositories, etc. The new program will also provide an opportunity for development of guidance on application of the methodology that will be of assistance to both safety assessors and regulators.

  17. Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1

    SciTech Connect

    Simonds, J.

    2007-11-06

    This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, administration facility, weigh scale, and various staging/storage areas. These facilities were designed and constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the Idaho National Laboratory (INL) facility for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams.

  18. Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1

    SciTech Connect

    Simonds, J.

    2007-11-06

    This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, administration facility, weigh scale, and various staging/storage areas. These facilities were designed and constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the Idaho National Laboratory (INL) facility for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams.

  19. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    SciTech Connect

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  20. Iraq nuclear facility dismantlement and disposal project

    SciTech Connect

    Cochran, J.R.; Danneels, J.; Kenagy, W.D.; Phillips, C.J.; Chesser, R.K.

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  1. Preliminary design of a biological treatment facility for trench water from a low-level radioactive waste disposal area at West Valley, New York

    SciTech Connect

    Rosten, R.; Malkumus, D.; Sonntag, T.; Sundquist, J.

    1993-03-01

    The New York State Energy Research and Development Authority (NYSERDA) owns and manages a State-Licensed Low-Level Radioactive Waste Disposal Area (SDA) at West Valley, New York. Water has migrated into the burial trenches at the SDA and collected there, becoming contaminated with radionuclides and organic compounds. The US Environmental Protection Agency issued an order to NYSERDA to reduce the levels of water in the trenches. A treatability study of the contaminated trench water (leachate) was performed and determined the best available technology to treat the leachate and discharge the effluent. This paper describes the preliminary design of the treatment facility that incorporates the bases developed in the leachate treatability study.

  2. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a)...

  3. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Records, Reports, Tests, and Inspections § 61.81 Tests at land disposal facilities. (a) Each...

  4. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  5. Composite analysis E-area vaults and saltstone disposal facilities

    SciTech Connect

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  6. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  7. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    SciTech Connect

    Cook, J.R.

    2000-03-13

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility.

  8. Fire risk analysis for a chemical agent disposal facility

    SciTech Connect

    Chang, J. ); Ho, V. ); Douthat, D. )

    1992-01-01

    The US Department of Defense (DOD) was directed by the Congress in the DOD Authorization Act of 1986 to destroy the nation's stockpile of lethal unitary chemical warfare agents and munitions. The stockpile consists of nerve agents and a blister agent in bulk storage containers, bombs, rockets, mines, projectiles, and mortar rounds stored at eight locations in the continental US and at Johnston Atoll in the Pacific Ocean. The chemical agent disposal facility is designed to destroy the agents safely. Serious fires in the facility can cause munition explosions, major equipment damages, and the damage of safety control systems whose functions are crucial in preventing agent release. A fire risk assessment is conducted to investigate frequencies, consequences, and mitigation methods of fires to enhance the design safety features of the agent disposal facility. This paper describes the fire risk analysis (FRA) performed in the system hazard analysis task for the facility and also presents highlights of the FRA results. Application can be made to the nuclear industry.

  9. Hazardous Waste Land Disposal Facility Assessment. Volume 1

    DTIC Science & Technology

    1988-09-01

    Facilities ( DALF ) at RVA" (USATHANA, 1984) provided the basis for the volume estimates for siting a disposal facility as discussed in Appendix 1.3. The... DALF also addressed on-site disposal options in addition to other technologies. This study supported the on-site disposal option by stating that a...impermeable bedrock do not exist at RMA. The DALF , drawing on the conclusions of the earlier WES 1983 report, recoumended a site in the northeast quarter of

  10. Geology of the Integrated Disposal Facility Trench

    SciTech Connect

    Reidel, Steve P.; Fecht, Karl R.

    2005-07-01

    This report describes the geology of the integrated Disposal Facility (IDF) Trench. The stratigraphy consists of some of the youngest sediments of the Missoula floods (younger than 770 ka). The lithology is dominated sands with minor silts and gravels that are largely unconsolidated. The stratigraphy can be subdivided into five geologic units that can be mapped throughout the trench. Four of the units were deposited by the Missoula floods and the youngest consists of windblown sand and silt. The sediment has little moisture and is consistent with that observed in the characterization boreholes. The sedimentary layers are flat lying and there are no faults or folds present. Two clastic dikes were encountered, one along the west wall and one that can be traced from the north to the southwall. The north-south clastic dike nearly bifurcates the trench but the west wall clastic dike can not be traced very far east into the trench. The classic dikes consist mainly of sand with clay-lined walls. The sediment in the dikes is compacted to partly cemented and are more resistant than the layered sediments.

  11. ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

    SciTech Connect

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-02-27

    The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

  12. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; Mike Lehto

    2010-05-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  13. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Lisa Harvego; Mike Lehto

    2010-02-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  14. Facility design, construction, and operation

    SciTech Connect

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l`Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l`Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec`s contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides` all of the basic information in these areas and reflects actual experience to date.

  15. Low-level radioactive waste disposal facility closure

    SciTech Connect

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. )

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  16. Probabilistic Modeling of Settlement Risk at Land Disposal Facilities - 12304

    SciTech Connect

    Foye, Kevin C.; Soong, Te-Yang

    2012-07-01

    The long-term reliability of land disposal facility final cover systems - and therefore the overall waste containment - depends on the distortions imposed on these systems by differential settlement/subsidence. The evaluation of differential settlement is challenging because of the heterogeneity of the waste mass (caused by inconsistent compaction, void space distribution, debris-soil mix ratio, waste material stiffness, time-dependent primary compression of the fine-grained soil matrix, long-term creep settlement of the soil matrix and the debris, etc.) at most land disposal facilities. Deterministic approaches to long-term final cover settlement prediction are not able to capture the spatial variability in the waste mass and sub-grade properties which control differential settlement. An alternative, probabilistic solution is to use random fields to model the waste and sub-grade properties. The modeling effort informs the design, construction, operation, and maintenance of land disposal facilities. A probabilistic method to establish design criteria for waste placement and compaction is introduced using the model. Random fields are ideally suited to problems of differential settlement modeling of highly heterogeneous foundations, such as waste. Random fields model the seemingly random spatial distribution of a design parameter, such as compressibility. When used for design, the use of these models prompts the need for probabilistic design criteria. It also allows for a statistical approach to waste placement acceptance criteria. An example design evaluation was performed, illustrating the use of the probabilistic differential settlement simulation methodology to assemble a design guidance chart. The purpose of this design evaluation is to enable the designer to select optimal initial combinations of design slopes and quality control acceptance criteria that yield an acceptable proportion of post-settlement slopes meeting some design minimum. For this specific

  17. Annual Summary of the Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Lehman, L. L.

    2011-01-11

    An annual summary on the adequacy of the Hanford Imnmobilized Low-Activity Waste (RLAW) Performance Assessment (PA) is required for each year in which a PA is not issued (DOE 0 435.1, Radioactive Waste Management; DOE M 435.1-1, Radioactive Waste Management Manual; DOE/ORP-2000-0 1, Maintenance Plan For The Hanford Immobilized Low-Activity Tank Waste Performance Assessment). The most recently approved PA is DOE/ORP-2000-24, Hanford Immobilized Low-Activity Waste Performance Assessment: 2001 Version. The ELAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (11DF), for the safe disposal of vitrified Hanford Site tank waste. More recently, a preliminary evaluation for the disposal of offsite low-level waste and mixed low-level waste was considered in 12 RPP- 15834, Integrated Disposal Facility Risk Assessment.

  18. Annual Summary of the Integrated Disposal Facility Performance Assessment 2009

    SciTech Connect

    Lehman, L. L.

    2010-09-21

    The U.S. Department of Energy (DOE) order on radioactive waste management (DOE 0 43 5. 1, Radioactive Waste Management) as well as DOE/ORP-2000-O 1 Rev. 1, Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment, require an annual summary on the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) in each year in which a PA is not issued. The most recent approved PA is DOE/ORP-2000-24 Rev. 0, Hanford Immobilized Low-Activity Waste Performance Assessment 2001 Version. The ILAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (IiDF), to safely dispose vitrified Hanford Site tank waste. More recently, a preliminary evaluation for the disposal of offsite low-level and mixed low-level waste was considered in R-PP-1 5834, Integrated Disposal Facility Risk Assessment.

  19. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE... radioactive wastes. (2) Radiation detection and monitoring instruments; and (3) Other equipment and devices...

  20. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE... radioactive wastes. (2) Radiation detection and monitoring instruments; and (3) Other equipment and devices...

  1. 10 CFR 61.81 - Tests at land disposal facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Tests at land disposal facilities. 61.81 Section 61.81 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE... radioactive wastes. (2) Radiation detection and monitoring instruments; and (3) Other equipment and devices...

  2. 300 Area Treated Effluent Disposal Facility (TEDF) Hazards Assessment

    SciTech Connect

    CAMPBELL, L.R.

    1999-01-15

    This document establishes the technical basis in support of emergency planning activities for the 300 Area Treated Effluent Disposal Facility. The technical basis for project-specific Emergency Action Levels and Emergency Planning Zone is demonstrated.

  3. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 2 2012-04-01 2012-04-01 false Exempt facility bonds: solid waste disposal... and Local Bonds § 1.142(a)(6)-1 Exempt facility bonds: solid waste disposal facilities. (a) In general... the completion of such integrated process. As of the issue date of the bonds used to finance the...

  4. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 2 2013-04-01 2013-04-01 false Exempt facility bonds: solid waste disposal... and Local Bonds § 1.142(a)(6)-1 Exempt facility bonds: solid waste disposal facilities. (a) In general... the completion of such integrated process. As of the issue date of the bonds used to finance the...

  5. 26 CFR 1.142(a)(6)-1 - Exempt facility bonds: solid waste disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 2 2014-04-01 2014-04-01 false Exempt facility bonds: solid waste disposal... and Local Bonds § 1.142(a)(6)-1 Exempt facility bonds: solid waste disposal facilities. (a) In general... the completion of such integrated process. As of the issue date of the bonds used to finance the...

  6. Annual Summary of the Integrated Disposal Facility Performance Assessment 2012

    SciTech Connect

    Khaleel, R.; Nichols, W. E.

    2012-12-27

    An annual summary of the adequacy of the Hanford Immobilized Low-Activity Waste (ILAW) Performance Assessment (PA) is required each year (DOE O 435.1 Chg 1,1 DOE M 435.1-1 Chg 1;2 and DOE/ORP-2000-013). The most recently approved PA is DOE/ORP-2000-24.4 The ILAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (IDF), for the safe disposal of vitrified Hanford Site tank waste.

  7. Environmental monitoring of the tumulus low-level waste disposal facilities at Oak Ridge National Laboratory

    SciTech Connect

    Morrissey, C.M.; Ashwood, T.L.

    1992-01-01

    The tumulus facilities at Oak Ridge National Laboratory (ORNL) were constructed beginning in 1987 as a means of above-grade disposal of low-level radioactive waste (LLW). The facilities consist of Tumulus I, Tumulus II, and the Interim Waste Management Facility (IWMF). They are designed to meet performance criteria that require no release of radioactive contaminants to the environment for a period of one hundred years. This paper describes the tumulus facilities, the environmental monitoring program, and what we have learned from the program over approximately three years of operation. Our data suggest that the tumulus facilities are an effective means of disposal of low-level radioactive waste. However, problems with high pH and the leaching of [sup 40]K, and potentially other elements from the concrete disposal pads and vaults, need to be addressed with regard to the long-term performance of the facilities.

  8. Construction, Startup and Operation of a New LLRW Disposal Facility in Andrews County, Texas - 12151

    SciTech Connect

    Van Vliet, James A.

    2012-07-01

    During this last year, Waste Control Specialists LLC (WCS) completed construction and achieved start of operations of a new low level radioactive waste (LLRW) disposal facility in Andrews County Texas. Disposal operations are underway for commercial LLRW, and start up evolutions are in progress for disposal of Department of Energy (DOE) LLRW. The overall approach to construction and start up are presented as well as some of the more significant challenges and how they were addressed to achieve initial operations of the first new commercial low level radioactive waste disposal facility in more than 30 years. The WCS disposal facility consists of two LLRW disposal cells, one for Texas Compact waste, and a separate disposal cell for DOE waste. Both disposal cells have very robust and unique designs. The cells themselves are constructed entirely in very low permeability red bed clay. The cell liners include a 0.91 meter thick clay liner meeting unprecedented permeability limits, 0.3 meter thick reinforced concrete barriers, as well as the standard geo-synthetic liners. Actions taken to meet performance criteria and install these liners will be discussed. Consistent with this highly protective landfill design, WCS chose to install a zero discharge site water management system. The considerations behind the design and construction of this system will be presented. Other activities essential to successful start of LLRW disposal operations included process and procedure development and refinement, staffing and staff development, and training. Mock ups were built and used for important evolutions and functions. Consistent with the extensive regulation of LLRW operations, engagement with the Texas Commission on Environmental Quality (TCEQ) was continuous and highly interactive. This included daily activity conference calls, weekly coordination calls and numerous topical conference calls and meetings. TCEQ staff and consultants frequently observed specific construction

  9. Air pollutants emissions from waste treatment and disposal facilities.

    PubMed

    Hamoda, Mohamed F

    2006-01-01

    This study examined the atmospheric pollution created by some waste treatment and disposal facilities in the State of Kuwait. Air monitoring was conducted in a municipal wastewater treatment plant, an industrial wastewater treatment plant established in a petroleum refinery, and at a landfill site used for disposal of solid wastes. Such plants were selected as models for waste treatment and disposal facilities in the Arabian Gulf region and elsewhere. Air measurements were made over a period of 6 months and included levels of gaseous emissions as well as concentrations of volatile organic compounds (VOCs). Samples of gas and bioaerosols were collected from ambient air surrounding the treatment facilities. The results obtained from this study have indicated the presence of VOCs and other gaseous pollutants such as methane, ammonia, and hydrogen sulphide in air surrounding the waste treatment and disposal facilities. In some cases the levels exceeded the concentration limits specified by the air quality standards. Offensive odors were also detected. The study revealed that adverse environmental impact of air pollutants is a major concern in the industrial more than in the municipal waste treatment facilities but sitting of municipal waste treatment and disposal facilities nearby the urban areas poses a threat to the public health.

  10. Readiness Assessment Plan, Hanford 200 areas treated effluent disposal facilities

    SciTech Connect

    Ulmer, F.J.

    1995-02-06

    This Readiness Assessment Plan documents Liquid Effluent Facilities review process used to establish the scope of review, documentation requirements, performance assessment, and plant readiness to begin operation of the Treated Effluent Disposal system in accordance with DOE-RLID-5480.31, Startup and Restart of Facilities Operational Readiness Review and Readiness Assessments.

  11. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria for classification of solid waste disposal facilities and practices. Solid waste disposal facilities or practices...

  12. 40 CFR 257.3 - Criteria for classification of solid waste disposal facilities and practices.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR CLASSIFICATION OF SOLID WASTE DISPOSAL FACILITIES AND PRACTICES Classification of Solid Waste Disposal Facilities and Practices § 257.3 Criteria for classification of solid waste disposal facilities and practices. Solid waste disposal facilities or practices...

  13. Verification of best available technology for the 300 Area Treated Effluent Disposal Facility (310 Facility)

    SciTech Connect

    Wagner, R.N.

    1994-09-26

    This compilation of Project L-045H reference materials documents that the 300 Area Treated Effluent Disposal Facility (TEDF, also designated the 310 Facility) was designed, built, and will be operated in accordance with the best available technology (BAT) identified in the Engineering Summary Report. The facility is intended for treatment of 300 Area process sewer wastewater. The following unit operations for 300 Area process sewer water treatment are specified as: influent receipt; iron co-precipitation and sludge handling for removal of heavy metals and initial suspended solids; ion exchanged for removal of mercury and other heavy metals; ultraviolet (UV)/peroxide treatment for destruction of organic compounds, cyanide, coliforms, sulfide, and nitrite; and effluent discharge to the Columbia River with pH monitoring/control capability.

  14. Annual Summary of the Integrated Disposal Facility Performance Assessment 2011

    SciTech Connect

    Lehman, L. L.

    2012-03-12

    An annual summary of the adequacy of the Hanford Immobilized Low-Activity Waste (ILAW) Performance Assessment (PA) is required each year (DOE O 435.1 Chg 1,1 DOE M 435.1-1 Chg 1,2 DOE/ORP-2000-013). The most recently approved PA is DOE/ORP-2000-24.4 The ILAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (IDF), for the safe disposal of vitrified Hanford Site tank waste. More recently, a preliminary evaluation for the disposal of offsite low-level waste and mixed low-level waste was considered in RPP-1583.

  15. Final closure of a low level waste disposal facility

    SciTech Connect

    Potier, J.M.

    1995-12-31

    The low-level radioactive waste disposal facility operated by the Agence Nationale pour la Gestion des Dechets Radioactifs near La Hague, France was opened in 1969 and is scheduled for final closure in 1996. The last waste package was received in June 1994. The total volume of disposed waste is approximately 525,000 m{sup 3}. The site closure consists of covering the disposal structures with a multi-layer impervious cap system to prevent rainwater from infiltrating the waste isolation system. A monitoring system has been set up to verify the compliance of infiltration rates with hydraulic performance objectives (less than 10 liters per square meter and per year).

  16. CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY

    SciTech Connect

    Jordan, J.; Flach, G.

    2012-03-29

    As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

  17. Subproject L-045H 300 Area Treated Effluent Disposal Facility

    SciTech Connect

    Not Available

    1991-06-01

    The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The 300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations.

  18. Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1

    SciTech Connect

    J. Simonds

    2006-09-01

    This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, admin facility, weigh scale, decon building, treatment systems, and various staging/storage areas. These facilities were designed and are being constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery Act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the central Idaho National Laboratory (INL) facilityyy for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams. This compliance demonstration document discusses the conceptual site model for the ICDF Complex area. Within this conceptual site model, the selection of the area for the ICDF Complex is discussed. Also, the subsurface stratigraphy in the ICDF Complex area is discussed along with the existing contamination beneath the ICDF Complex area. The designs for the various ICDF Complex facilities are also included in this compliance demonstration document. These design discussions are a summary of the design as presented in the Remedial Design/Construction Work Plans for the ICDF landfill and evaporation pond and the Staging, Storage, Sizing, and Treatment Facility. Each of the major facilities or systems is described including the design criteria.

  19. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  20. Iodine-129 Dose in LLW Disposal Facility Performance Assessments

    SciTech Connect

    Wilhite, E.L.

    1999-10-15

    Iodine-129 has the lowest Performance Assessment derived inventory limit in SRS disposal facilities. Because iodine is concentrated in the body to one organ, the thyroid, it has been thought that dilution with stable iodine would reduce the dose effects of 129I.Examination of the dose model used to establish the Dose conversion factor for 129I shows that, at the levels considered in performance assessments of low-level waste disposal facilities, the calculated 129I dose already accounts for ingestion of stable iodine. At higher than normal iodine ingestion rates, the uptake of iodine by the thyroid itself decrease, which effectively cancels out the isotopic dilution effect.

  1. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect

    David Duncan

    2011-05-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  2. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2011-03-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  3. Development of high integrity, maximum durability concrete structures for LLW disposal facilities

    SciTech Connect

    Taylor, W.P.

    1992-05-01

    A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

  4. Development of high integrity, maximum durability concrete structures for LLW disposal facilities

    SciTech Connect

    Taylor, W.P. , Inc., Charlotte, NC )

    1992-01-01

    A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

  5. Support of the Iraq nuclear facility dismantlement and disposal program

    SciTech Connect

    Coates, Roger; Cochran, John; Danneels, Jeff; Chesser, Ronald; Phillips, Carlton; Rogers, Brenda

    2007-07-01

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

  6. Design, construction, and operations experience with the SWSA 6 (Solid Waste Storage Area) Tumulus Disposal Demonstration

    SciTech Connect

    Van Hoesen, S.D.; Van Cleve, J.E.; Wylie, A.N.; Williams, L.C.; Bolinsky, J.

    1988-01-01

    Efforts are underway at the Department of Energy facilities in Oak Ridge to improve the performance of radioactive waste disposal facilities. An engineered disposal concept demonstration involving placement of concrete encased waste on a monitored concrete pad with an earthen cover is being conducted. The design, construction, and operations experience with this project, the SWSA 6 Tumulus Disposal Demonstration, is described. 1 fig., 1 tab.

  7. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  8. Iraq nuclear facility dismantlement and disposal project (NDs Project).

    SciTech Connect

    Cochran, John Russell

    2010-06-01

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

  9. Natural hazards phenomena mitigation with respect to seismic hazards at the Environmental Restoration Disposal Facility

    SciTech Connect

    Reidel, S.P.

    1994-01-06

    This report provides information on the seismic hazard for design of the proposed Environmental Restoration Disposal Facility (ERDF), a facility designed for the disposal of wastes generated during the cleanup of Hanford Site aggregate areas. The preferred ERDF site is located south and east of 200 East and 200 West Areas. The Washington State Groundwater Protection Program (WAC 173-303-806 (4)(a)(xxi)) requires that the characteristics of local and regional hydrogeology be defined. A plan for that work has been developed (Weekes and Borghese 1993). In addition, WAC 173-303-282 provides regulatory guidance on siting a dangerous waste facility, and US Department of Energy (DOE) Order 5480.28 requires consideration of natural phenomena hazards mitigation for DOE sites and facilities. This report provides information to evaluate the ERDF site with respect to seismic hazard. The ERDF will be a Corrective Action Management Unit (CAMU) as defined by 40 CFR 260.10.

  10. Estimated Particulate Emissions By Wind Erosion From the Indiana Harbor Confined Disposal Facility

    USDA-ARS?s Scientific Manuscript database

    A Confined Disposal Facility (CDF) is being designed for contaminated sediments dredged from the Indiana Harbor Canal at East Chicago, IN. The sediment will be placed in two cells enclosed by earthern berms about 9 m tall and cover about 36 hectares. The purposes of this study were to a) determine...

  11. Environmental management of quarries as waste disposal facilities.

    PubMed

    El-Fadel, M; Sadek, S; Chahine, W

    2001-04-01

    Problems associated with the disposal of municipal solid waste have become a source of public concern worldwide as awareness of potential adverse environmental impacts and health threats from solid waste has increased. Communities are concerned about the generation and management of solid waste to the extent of refusing to allow new disposal facilities near their homes, often after witnessing the legacy of existing facilities. Under these conditions, the development of national policies for the management of solid waste becomes highly political, all while requiring appropriate technical solutions that ensure environmental protection and proper management plans that support an acceptable solution for the disposal of municipal solid waste. In some locations, the conversion of old quarries into well-engineered and controlled landfills appears as a promising solution to a continuously increasing problem, at least for many decades to come. This paper describes the environmental impacts associated with solid waste disposal in a converted quarry site and the mitigation measures that can be adopted to alleviate potential adverse impacts. Environmental management and monitoring plans are also discussed in the context of ensuring adequate environmental protection during and after the conversion process.

  12. The Groundwater Geochemistry of Waste Disposal Facilities

    NASA Astrophysics Data System (ADS)

    Bjerg, P. L.; Albrechtsen, H.-J.; Kjeldsen, P.; Christensen, T. H.; Cozzarelli, I. M.

    2003-12-01

    Landfills of solid waste are abundant sources of groundwater pollution. The potential for generatingstrongly contaminated leachate from landfill waste is very substantial. Even for small landfills the timescale can be measured in decades or centuries. This indicates that waste dumps with no measures to control leachate entrance into the groundwater may constitute a source of groundwater contamination long after dumping has ceased. In addition to these dumps, engineered landfills with liners and leachate collection systems may also constitute a source of groundwater contamination due to inadequate design, construction, and maintenance, resulting in the leakage of leachate.Landfills may pose several environmental problems (explosion hazards, vegetation damage, dust and air emissions, etc.), but groundwater pollution by leachate is considered to be the most important one and the focus of this chapter. Landfills differ significantly depending on the waste they receive: mineral waste landfills for combustion ashes, hazardous waste landfills, specific industrial landfills serving a single industry, or municipal waste landfills receiving a mixture of municipal waste, construction, and demolition waste, waste from small industries and minor quantities of hazardous waste. The latter type of landfill (termed "old landfills" in this chapter) is very common all over the world. Municipal landfills are characterized by a high content of organic waste that affects the biogeochemical processes in the landfill body and the generation of strongly anaerobic leachate with a high content of dissolved organic carbon, salts, ammonium, and organic compounds and metals released from the waste.This chapter describes the biogeochemistry of a landfill leachate plume as it emerges from the bottom of a landfill and migrates in an aquifer. The landfill hydrology, source composition, and spreading of contaminants are described in introductory sections. The focus of this chapter is on

  13. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect

    Cook, J.R.; Hunt, P.D.

    1994-04-15

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

  14. 76 FR 55256 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-07

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BD04 Definition of Solid Waste Disposal Facilities for Tax... published in the Federal Register on Friday, August 19, 2011, on the definition of solid waste disposal... solid waste disposal facilities and to taxpayers that use those facilities. DATES: This correction...

  15. Environmental monitoring of low-level radioactive waste disposal facility

    SciTech Connect

    Shum, E.Y.; Starmer, R.J.; Young, M.H.

    1989-12-01

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance.

  16. Bird mortality in oil field wastewater disposal facilities.

    PubMed

    Ramirez, Pedro

    2010-11-01

    Commercial and centralized oilfield wastewater disposal facilities (COWDFs) are used in the Western United States for the disposal of formation water produced from oil and natural gas wells. In Colorado, New Mexico, Utah, and Wyoming, COWDFs use large evaporation ponds to dispose of the wastewater. Birds are attracted to these large evaporation ponds which, if not managed properly, can cause wildlife mortality. The U.S. Fish and Wildlife Service (USFWS) and the U.S. Environmental Protection Agency (EPA) conducted 154 field inspections of 28 COWDFs in Wyoming from March 1998 through September 2008 and documented mortality of birds and other wildlife in 9 COWDFs. Of 269 bird carcasses recovered from COWDFs, grebes (Family Podicipedidae) and waterfowl (Anatidae) were the most frequent casualties. Most mortalities were attributed to oil on evaporation ponds, but sodium toxicity and surfactants were the suspected causes of mortality at three COWDFs. Although the oil industry and state and federal regulators have made much progress in reducing bird mortality in oil and gas production facilities, significant mortality incidents continue in COWDFs, particularly older facilities permitted in the early 1980's. Inadequate operation and management of these COWDFs generally results in the discharge of oil into the large evaporation ponds which poses a risk for birds and other wildlife.

  17. Bird Mortality in Oil Field Wastewater Disposal Facilities

    NASA Astrophysics Data System (ADS)

    Ramirez, Pedro

    2010-11-01

    Commercial and centralized oilfield wastewater disposal facilities (COWDFs) are used in the Western United States for the disposal of formation water produced from oil and natural gas wells. In Colorado, New Mexico, Utah, and Wyoming, COWDFs use large evaporation ponds to dispose of the wastewater. Birds are attracted to these large evaporation ponds which, if not managed properly, can cause wildlife mortality. The U.S. Fish and Wildlife Service (USFWS) and the U.S. Environmental Protection Agency (EPA) conducted 154 field inspections of 28 COWDFs in Wyoming from March 1998 through September 2008 and documented mortality of birds and other wildlife in 9 COWDFs. Of 269 bird carcasses recovered from COWDFs, grebes (Family Podicipedidae) and waterfowl (Anatidae) were the most frequent casualties. Most mortalities were attributed to oil on evaporation ponds, but sodium toxicity and surfactants were the suspected causes of mortality at three COWDFs. Although the oil industry and state and federal regulators have made much progress in reducing bird mortality in oil and gas production facilities, significant mortality incidents continue in COWDFs, particularly older facilities permitted in the early 1980’s. Inadequate operation and management of these COWDFs generally results in the discharge of oil into the large evaporation ponds which poses a risk for birds and other wildlife.

  18. Licensing procedures for Low-Level Waste disposal facilities

    SciTech Connect

    Roop, R.D.; Van Dyke, J.W.

    1985-09-01

    This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs.

  19. Performance assessment for the class L-II disposal facility

    SciTech Connect

    1997-03-01

    This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

  20. Review of systemization of the Tooele Chemical Agent Disposal Facility

    SciTech Connect

    1996-07-01

    In 1993, at Tooele Army Depot, Utah, the Army completed construction of the Tooele Chemical Agent Disposal Facility (TOCDF), the first complete facility for destruction of lethal unitary chemical agents and munitions to be built in the continental United States. The TOCDF will employ the Army`s baseline incineration system to destroy the depot`s increment of the nation`s aging unitary chemical stockpile. This book assesses Army changes and improvements to the TOCDF in response to recommendations contained in earlier reports of the committee. It assesses aspects of the facility`s readiness for safe agent handling and destruction operations, its agent monitoring system, and its site specific risk assessment.

  1. International low level waste disposal practices and facilities

    SciTech Connect

    Nutt, W.M.

    2011-12-19

    The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

  2. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    SciTech Connect

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 × 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 × 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 × 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo

  3. Development of an Environmental Safety Case for a Geological Disposal Facility in the UK

    NASA Astrophysics Data System (ADS)

    Bailey, L.; Clark, H.; Wellstead, M.

    2012-04-01

    Geological disposal is the UK policy for the long-term management of higher activity radioactive waste. The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal. The implementation process is founded on the principles of voluntarism and partnership and the UK Government has set in place a process that encourages communities to participate in the siting process. Developing an environmental safety case (ESC) that gives confidence that a geological disposal facility (GDF) for higher activity radioactive wastes will remain passively safe for hundreds of thousands of years after the facility has been closed, and is no longer actively maintained, is an important and challenging part of the programme to implement geological disposal. Our approach for building confidence in long-term safety is to use multiple barriers to isolate and contain the wastes and to explain our confidence in the performance of these barriers by developing a multi-factor safety case. We will develop a safety case based on varied and different lines of reasoning, including both quantitative aspects and qualitative arguments. We will use a range of safety arguments to support the ESC, drawing on underpinning science and engineering. We have published a generic ESC (that is not specific to any site or disposal facility design) that considers the long-term safety of illustrative generic disposal facility design examples in stylised geological environments. This generic ESC explains how engineered and natural barriers can work together to isolate and contain the radioactivity in the wastes. The safety arguments in the generic ESC are supported by calculations using a simple model that is illustrative of a broad range of disposal facility designs and geological environments. The generic ESC provides a benchmark enabling us to undertake disposability assessments for waste packages, without

  4. Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

    SciTech Connect

    Ledoux, M. R.; Cade, M. S.

    2002-02-25

    Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations.

  5. Z-Area Saltstone Disposal Facility groundwater monitoring report

    SciTech Connect

    1995-12-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Industrial Waste Permit IWP-217 and for other constituents as part of the Savannah River Site Groundwater Monitoring Program. During third quarter 1995, no constituents were reported above final Primary Drinking Water Standards or Savannah River Site flagging criteria. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  6. Integrated Disposal Facility FY2011 Glass Testing Summary Report. Erratum

    SciTech Connect

    Smith, Gary L.

    2016-09-06

    This report refers to or contains Kg values for glasses LAWA44, LAWB45 and LAWC22 affected by calculations errors as identified by Papathanassiu et al. (2011). The corrected Kg values are reported in an erratum included in the revised version of the original report. The revised report can be referenced as follows: Pierce E. M. et al. (2004) Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. PNNL-14805 Rev. 0 Erratum. Pacific Northwest National Laboratory, Richland, WA, USA.

  7. Integrated Disposal Facility FY 2012 Glass Testing Summary Report, Erratum

    SciTech Connect

    Smith, Gary L.

    2016-09-02

    This report refers to or contains Kg values for glasses LAWA44, LAWB45 and LAWC22 affected by calculations errors as identified by Papathanassiu et al. (2011) The corrected Kg values are reported in an erratum included in the revised version of the original report. The revised report can be referenced as follows: Pierce E. M. et al. (2004) Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. PNNL-14805 Rev. 0 Erratum. Pacific Northwest National Laboratory, Richland, WA, USA.

  8. Generation and release of radioactive gases in LLW disposal facilities

    SciTech Connect

    Yim, M.S.; Simonson, S.A.

    1995-02-01

    The atmospheric release of radioactive gases from a generic engineered LLW disposal facility and its radiological impacts were examined. To quantify the generation of radioactive gases, detailed characterization of source inventory for carbon-14, tritium, iodine-129, krypton-85, and radon-222, was performed in terms of their activity concentrations; their distribution within different waste classes, waste forms and containers; and their subsequent availability for release in volatile or gaseous form. The generation of gases was investigated for the processes of microbial activity, radiolysis, and corrosion of waste containers and metallic components in wastes. The release of radionuclides within these gases to the atmosphere was analyzed under the influence of atmospheric pressure changes.

  9. 40 CFR 61.220 - Designation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Emissions From the Disposal of Uranium Mill Tailings § 61.220 Designation of facilities. (a) The provisions of this subpart apply to owners and operators of all sites that are used for the disposal of tailings..., commonly referred to as uranium mills and their associated tailings, that are listed in, or designated by...

  10. Economics of a small-volume low-level radioactive waste disposal facility

    SciTech Connect

    Not Available

    1993-04-01

    This report was prepared by the US Department of Energy National Low-Level Waste Management Program to present the results of a life-cycle cost analysis of a low-level radioactive waste disposal facility, including all support facilities, beginning in the preoperational phase and continuing through post-closure care. The disposal technology selected for this report is earth-covered concrete vaults, which use reinforced concrete vaults constructed above grade and an earth cover constructed at the end of the operational period for permanent closure. The report develops a design, cost estimate, and schedule for the base case and eight alternative scenarios involving changes in total disposal capacity, operating life, annual disposal rate, source of financing and long-term interest rates. The purpose of this analysis of alternatives is to determine the sensitivity of cost to changes in key analytical or technical parameters, thereby evaluating the influence of a broad range of conditions. The total estimated cost of each alternative is estimated and a unit disposal charge is developed.

  11. (Low-level waste disposal facility siting and site characterization)

    SciTech Connect

    Mezga, L.J.; Ketelle, R.H.; Pin, F.G.; Van Hoesen, S.D.

    1985-10-25

    A US team consisting of representatives of Oak Ridge National Laboratory (ORNL), Savannah River Plant (SRP), Savannah river Laboratory (SRL), and the Department of Energy Office of Defense Waste and Byproducts Management participated in the fourth meeting held under the US/French Radioactive Waste Management Agreement between the US Department of Energy and the Commissariat a l'Energie Atomique. This meeting, held at Agence Nationale pour les Gestion des Dechets Radioactifs' (ANDRA's) Headquarters in Paris, was a detailed, technical topical workshop focusing on Low-Level Waste Disposal Facility Siting and Site Characterization.'' The meeting also included a visit to the Centre de la Manche waste management facility operated by ANDRA to discuss and observe the French approach to low-level waste management. The final day of the meeting was spent at the offices of Societe Generale pour les Techniques Nouvelles (SGN) discussing potential areas of future cooperation and exchange. 20 figs.

  12. From NIMBY to YIMBY: How generators can support siting LLRW disposal facilities

    SciTech Connect

    Hoffman, J.P.

    1995-05-01

    The most frequently head complaint about siting low-level radioactive waste disposal facilities is the NIMBY (Not In My Back Yard) syndrome. The producers or generators of this waste can help move public opinion form NIMBY to YIMBY (YES! In MY Back Yard!). Generators of low-level radioactive waste often believe it is the responsibility of other organizations to site disposal facilities for the waste, and that their role is to assure the technical aspects of the facility, such as acceptability criteria for the various waste forms, are clearly defined. In reality, generators, using a properly designed and effectively implemented communications plan, can be the most effective advocates for siting a facility. The communications plan must include the following elements: an objective focusing on the importance of generators becoming vocal and active; clearly defined and crafted key messages; specifically defined and targeted audiences for those messages; and speaker training which includes how to communicate with hostile or concerned audiences about a subject they perceive as very risky. Generators must develop coalitions with other groups and form a grassroots support organization. Finally, opportunities must be developed to deliver these messages using a variety of means. Written materials should be distributed often to keep the need for disposal capability in the public`s mind. Can we get from NIMBY to YIMBY? It is difficult, but doable--especially with support from the people who make the waste in the first place.

  13. EnergySolution's Clive Disposal Facility Operational Research Model - 13475

    SciTech Connect

    Nissley, Paul; Berry, Joanne

    2013-07-01

    EnergySolutions owns and operates a licensed, commercial low-level radioactive waste disposal facility located in Clive, Utah. The Clive site receives low-level radioactive waste from various locations within the United States via bulk truck, containerised truck, enclosed truck, bulk rail-cars, rail boxcars, and rail inter-modals. Waste packages are unloaded, characterized, processed, and disposed of at the Clive site. Examples of low-level radioactive waste arriving at Clive include, but are not limited to, contaminated soil/debris, spent nuclear power plant components, and medical waste. Generators of low-level radioactive waste typically include nuclear power plants, hospitals, national laboratories, and various United States government operated waste sites. Over the past few years, poor economic conditions have significantly reduced the number of shipments to Clive. With less revenue coming in from processing shipments, Clive needed to keep its expenses down if it was going to maintain past levels of profitability. The Operational Research group of EnergySolutions were asked to develop a simulation model to help identify any improvement opportunities that would increase overall operating efficiency and reduce costs at the Clive Facility. The Clive operations research model simulates the receipt, movement, and processing requirements of shipments arriving at the facility. The model includes shipment schedules, processing times of various waste types, labor requirements, shift schedules, and site equipment availability. The Clive operations research model has been developed using the WITNESS{sup TM} process simulation software, which is developed by the Lanner Group. The major goals of this project were to: - identify processing bottlenecks that could reduce the turnaround time from shipment arrival to disposal; - evaluate the use (or idle time) of labor and equipment; - project future operational requirements under different forecasted scenarios. By identifying

  14. Quality assurance guidance for a low-level radioactive waste disposal facility

    SciTech Connect

    Pittiglio, C.L. Jr.; Hedges, D.

    1991-04-01

    This document provides guidance to an applicant on meeting the quality control (QC) requirements of 10 CFR 61.12(j) for a low-level radioactive waste (LLRW) disposal facility. The QC requirements, plus audits and managerial controls requirements, establish the need for developing a quality assurance (QA) program and the guidance provided herein. The criteria developed for this document are similar to the criteria developed for Appendix B to Title 10 of the Code of Federal Regulations (10 CFR) Part 50. Although Appendix B is not a regulatory requirement for an LLRW disposal facility, the criteria that were developed for 10 CFR Part 50 are basic to any QA program. This document establishes QA guidance for the design, construction, and operation of those structures, engineered or natural systems, and components whose function is required to meet the performance objectives of Subpart C of 10 CFR Part 61 and to limit exposure to or release of radioactivity. 7 refs.

  15. Design and Installation of a Disposal Cell Cover Field Test

    SciTech Connect

    Benson, C.H.; Waugh, W.J.; Albright, W.H.; Smith, G.M.; Bush, R.P.

    2011-02-27

    The U.S. Department of Energy’s Office of Legacy Management (LM) initiated a cover assessment project in September 2007 to evaluate an inexpensive approach to enhancing the hydrological performance of final covers for disposal cells. The objective is to accelerate and enhance natural processes that are transforming existing conventional covers, which rely on low-conductivity earthen barriers, into water balance covers, that store water in soil and release it as soil evaporation and plant transpiration. A low conductivity cover could be modified by deliberately blending the upper layers of the cover profile and planting native shrubs. A test facility was constructed at the Grand Junction, Colorado, Disposal Site to evaluate the proposed methodology. The test cover was constructed in two identical sections, each including a large drainage lysimeter. The test cover was constructed with the same design and using the same materials as the existing disposal cell in order to allow for a direct comparison of performance. One test section will be renovated using the proposed method; the other is a control. LM is using the lysimeters to evaluate the effectiveness of the renovation treatment by monitoring hydrologic conditions within the cover profile as well as all water entering and leaving the system. This paper describes the historical experience of final covers employing earthen barrier layers, the design and operation of the lysimeter test facility, testing conducted to characterize the as-built engineering and edaphic properties of the lysimeter soils, the calibration of instruments installed at the test facility, and monitoring data collected since the lysimeters were constructed.

  16. Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

    SciTech Connect

    Shank, D.R.

    1995-02-14

    The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

  17. Near-Field Hydrology Data Package for the Integrated Disposal Facility 2005 Performance Assessment

    SciTech Connect

    Meyer, Philip D.; Saripalli, Prasad; Freedman, Vicky L.

    2004-06-25

    CH2MHill Hanford Group, Inc. (CHG) is designing and assessing the performance of an Integrated Disposal Facility (IDF) to receive immobilized low-activity waste (ILAW), Low-Level and Mixed Low-Level Wastes (LLW/MLLW), and the Waste Treatment Plant (WTP) melters used to vitrify the ILAW. The IDF Performance Assessment (PA) assesses the performance of the disposal facility to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface water resources, and inadvertent intruders. The PA requires prediction of contaminant migration from the facilities, which is expected to occur primarily via the movement of water through the facilities and the consequent transport of dissolved contaminants in the pore water of the vadose zone. Pacific Northwest National Laboratory (PNNL) assists CHG in its performance assessment activities. One of PNNL’s tasks is to provide estimates of the physical, hydraulic, and transport properties of the materials comprising the disposal facilities and the disturbed region around them. These materials are referred to as the near-field materials. Their properties are expressed as parameters of constitutive models used in simulations of subsurface flow and transport. In addition to the best-estimate parameter values, information on uncertainty in the parameter values and estimates of the changes in parameter values over time are required to complete the PA. These parameter estimates and information were previously presented in a report prepared for the 2001 ILAW PA. This report updates the parameter estimates for the 2005 IDF PA using additional information and data collected since publication of the earlier report.

  18. Recharge Data Package for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Fayer, Michael J.; Szecsody, Jim E.

    2004-06-30

    Pacific Northwest National Laboratory assisted CH2M Hill Hanford Group, Inc., (CHG) by providing estimates of recharge rates for current conditions and long-term scenarios involving disposal in the Integrated Disposal Facility (IDF). The IDF will be located in the 200 East Area at the Hanford Site and will receive several types of waste including immobilized low-activity waste. The recharge estimates for each scenario were derived from lysimeter and tracer data collected by the IDF PA Project and from modeling studies conducted for the project. Recharge estimates were provided for three specific site features (the surface barrier; possible barrier side slopes; and the surrounding soil) and four specific time periods (pre-Hanford; Hanford operations; surface barrier design life; post-barrier design life). CHG plans to conduct a performance assessment of the latest IDF design and call it the IDF 2005 PA; this recharge data package supports the upcoming IDF 2005 PA.

  19. Disposable Diaper Absorbency: Improvements via Advanced Designs.

    PubMed

    Helmes, C Tucker; O'Connor, Robert; Sawyer, Larry; Young, Sharon

    2014-08-01

    Absorbency effectiveness in diapers has improved significantly in recent years with the advent of new ingredient combinations and advanced design features. With these features, many leading products maintain their dryness performance overnight. Considering the importance of holding liquid away from the skin, ongoing research in diaper construction focuses on strategies to increase the effectiveness to capture liquid and help avoid rewetting of infant skin. The layout and design of a disposable diaper allows for distribution of absorbency features where they can provide the optimal benefit. Clinical evidence indicates materials can keep moisture away from the skin in the diapered area, helping maintain proper skin hydration, minimizing irritation, and contributing to reduced rates of diaper rash.

  20. Financial Assurance Requirements for Hazardous Waste Treatment, Storage and Disposal Facilities

    EPA Pesticide Factsheets

    The Resource Conservation and Recovery Act (RCRA) requires all treatment, storage and disposal facilities (TSDFs) to demonstrate that they will have the financial resources to properly close the facility

  1. Aquatic facility design-designing for Atlantis?

    PubMed

    Bartlett, Doreen H

    2005-01-01

    The requirements for aquatic facility design differ greatly from those of a rodent facility. The author discusses factors to consider when planning new construction of an aquatic facility or renovating space to house aquatic species.

  2. Designing open water disposal for dredged muddy sediments

    NASA Astrophysics Data System (ADS)

    McAnally, William H.; Adamec, Stephen A.

    1987-11-01

    Open water disposal of muddy sediments in the estuarine environment is practiced to minimize dredging costs and to preserve contained disposal site capacity. Open water sites are usually either dispersive or retentive. Dispersive sites are used in the expectation that disposed sediments will not remain there, but will be transported out of the site, leaving room for additional disposal. Retentive sites are designed to ensure that disposed sediments mostly remain within the site. Choice of one of these approaches depends on the site character, sediment character, and disposal quantities. Design of disposal management plans for both site types is accomplished by use of field observations, laboratory tests, and numerical modeling. Three disposal site studies illustrate the methods used. At the Alcatraz site in San Francisco Bay, a dispersive condition is maintained by use of constraints on dredged mud characteristics that were developed from laboratory tests on erosion rates and from numerical modeling of the dump process. Field experiments were designed to evaluate the management procedure. In Corpus Christi Bay a numerical model was used to determine how much disposed sediment returns to the navigation channel, and to devise a location for disposal that will minimize that return. In Puget Sound a model has been used to ensure that most of the disposed material remains in the site. New techniques, including a piped disposal through 60 m of water, were investigated.

  3. Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility

    SciTech Connect

    BURBANK, D.A.

    2000-08-31

    This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

  4. 76 FR 55255 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-07

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BD04 Definition of Solid Waste Disposal Facilities for Tax... the Federal Register on Friday, August 19, 2011, on the definition of solid waste disposal facilities... regulations provide guidance to State and local governments that issue tax-exempt bonds to finance solid...

  5. 40 CFR 268.7 - Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... requirements for generators, treaters, and disposal facilities. 268.7 Section 268.7 Protection of Environment... Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities. (a) Requirements for generators: (1) A generator of hazardous waste must determine if the waste has to be treated...

  6. 40 CFR 268.7 - Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... requirements for generators, treaters, and disposal facilities. 268.7 Section 268.7 Protection of Environment... Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities. (a) Requirements for generators: (1) A generator of hazardous waste must determine if the waste has to be treated...

  7. 40 CFR 268.7 - Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... requirements for generators, treaters, and disposal facilities. 268.7 Section 268.7 Protection of Environment... Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities. (a) Requirements for generators: (1) A generator of hazardous waste must determine if the waste has to be treated...

  8. 40 CFR 268.7 - Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... requirements for generators, treaters, and disposal facilities. 268.7 Section 268.7 Protection of Environment... Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities. (a) Requirements for generators: (1) A generator of hazardous waste must determine if the waste has to be treated...

  9. 40 CFR 268.7 - Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... requirements for generators, treaters, and disposal facilities. 268.7 Section 268.7 Protection of Environment... Testing, tracking, and recordkeeping requirements for generators, treaters, and disposal facilities. (a) Requirements for generators: (1) A generator of hazardous waste must determine if the waste has to be treated...

  10. Design requirements document for project W-520, immobilized low-activity waste disposal

    SciTech Connect

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  11. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...) The boundaries and locations of each disposal unit (e.g., trenches) must be accurately located and... forth in the approved site closure plan must be carried out as each disposal unit (e.g., each trench)...

  12. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...) The boundaries and locations of each disposal unit (e.g., trenches) must be accurately located and... forth in the approved site closure plan must be carried out as each disposal unit (e.g., each trench)...

  13. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...) The boundaries and locations of each disposal unit (e.g., trenches) must be accurately located and... forth in the approved site closure plan must be carried out as each disposal unit (e.g., each trench)...

  14. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ...) The boundaries and locations of each disposal unit (e.g., trenches) must be accurately located and... forth in the approved site closure plan must be carried out as each disposal unit (e.g., each trench)...

  15. 10 CFR 61.52 - Land disposal facility operation and disposal site closure.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...) The boundaries and locations of each disposal unit (e.g., trenches) must be accurately located and... forth in the approved site closure plan must be carried out as each disposal unit (e.g., each trench)...

  16. Performance assessment for a hypothetical low-level waste disposal facility

    SciTech Connect

    Smith, C.S.; Rohe, M.J.; Ritter, P.D.

    1997-01-01

    Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

  17. Radiocarbon signal of a low and intermediate level radioactive waste disposal facility in nearby trees.

    PubMed

    Janovics, R; Kelemen, D I; Kern, Z; Kapitány, S; Veres, M; Jull, A J T; Molnár, M

    2016-03-01

    Tree ring series were collected from the vicinity of a Hungarian radioactive waste treatment and disposal facility and from a distant control background site, which is not influenced by the radiocarbon discharge of the disposal facility but it represents the natural regional (14)C level. The (14)C concentration of the cellulose content of tree rings was measured by AMS. Data of the tree ring series from the disposal facility was compared to the control site for each year. The results were also compared to the (14)C data of the atmospheric (14)C monitoring stations at the disposal facility and to international background measurements. On the basis of the results, the excess radiocarbon of the disposal facility can unambiguously be detected in the tree from the repository site. Copyright © 2016 Elsevier Ltd. All rights reserved.

  18. Developing a low-level radioactive waste disposal facility in Connecticut: Update on progress and new directions

    SciTech Connect

    Gingerich, R.E.

    1993-03-01

    Connecticut is a member of the Northeast Interstate Low-Level Radioactive Waste Management Compact (Northeast LLRW Compact). The other member of the Northeast LLRW Compact is New Jersey. The Northeast Interstate Low-Level Radioactive Waste Commission (Northeast Compact Commission), the Northeast LLRW Compact`s governing body, has designated both Connecticut and New Jersey as host states for disposal facilities. The Northeast Compact Commission has recommended that, for purposes of planning for each state`s facility, the siting agency for the state should use projected volumes and characteristics of the LLW generated in its own state. In 1987 Connecticut enacted legislation that assigns major responsibilities for developing a LLW disposal facility in Connecticut to the Connecticut Hazardous Waste Management Service (CHWMS). The CHWMS is required to: prepare and revise, as necessary, a LLW Management Plan for the state; select a site for a LLW disposal facility; select a disposal technology to be used at the site; select a firm to obtain the necessary approvals for the facility and to develop and operate it; and serve as the custodial agency for the facility. This paper discusses progress in developing a facility.

  19. Climate change in safety assessment of a surface disposal facility

    NASA Astrophysics Data System (ADS)

    Leterme, B.

    2012-04-01

    The Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) aims to develop a surface disposal facility for LILW-SL in Dessel (North-East of Belgium). Given the time scale of interest for the safety assessment (several millennia), a number of parameters in the modelling chain near field - geosphere - biosphere may be influenced by climate change. The present study discusses how potential climate change impact was accounted for the following quantities: (i) near field infiltration through the repository earth cover, (ii) partial pressure of CO2 in the water infiltrating the cover and draining the concrete, and (iii) groundwater recharge in the vicinity of the site. For these three parameters, the impact of climate change is assessed using climatic analogue stations, i.e. stations presently under climatic conditions corresponding to a given climate state. Results indicate that : (i) Using Gijon (Spain) as representative analogue station for the next millennia, infiltration at the bottom of the soil layer towards the modules of the facility is expected to increase (from 346 to 413 mm/y) under a subtropical climate. Although no colder climate is foreseen in the next 10 000 years, the approach was also tested with analogue stations for a colder climate state. Using Sisimiut (Greenland) as representative analogue station, infiltration is expected to decrease (109 mm/y). (ii) Due to changes of the partial pressure of CO2 in the soil water, cement degradation is estimated to occur more rapidly under a warmer climate. (iii) A decrease of long-term annual average groundwater recharge by 12% was simulated using Gijon representative analogue (from 314 to 276 mm), although total rainfall was higher (947 mm) in the warmer climate compared to the current temperate climate (899 mm). For a colder climate state, groundwater recharge simulated for the representative analogue Sisimiut showed a decrease by 69% compared to current climate conditions. The

  20. TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

    SciTech Connect

    Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

    1998-10-14

    Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides.

  1. 40 CFR 61.190 - Designation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... these facilities: The Feed Materials Production Center, Fernald, Ohio; the Niagara Falls Storage Site... subpart apply to the design and operation of all storage and disposal facilities for radium-containing material (i.e., byproduct material as defined under section 11.e(2) of the Atomic Energy Act of 1954...

  2. 40 CFR 61.190 - Designation of facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... these facilities: The Feed Materials Production Center, Fernald, Ohio; the Niagara Falls Storage Site... subpart apply to the design and operation of all storage and disposal facilities for radium-containing material (i.e., byproduct material as defined under section 11.e(2) of the Atomic Energy Act of 1954...

  3. 40 CFR 61.190 - Designation of facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... these facilities: The Feed Materials Production Center, Fernald, Ohio; the Niagara Falls Storage Site... subpart apply to the design and operation of all storage and disposal facilities for radium-containing material (i.e., byproduct material as defined under section 11.e(2) of the Atomic Energy Act of 1954...

  4. 40 CFR 61.190 - Designation of facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... these facilities: The Feed Materials Production Center, Fernald, Ohio; the Niagara Falls Storage Site... subpart apply to the design and operation of all storage and disposal facilities for radium-containing material (i.e., byproduct material as defined under section 11.e(2) of the Atomic Energy Act of 1954...

  5. 40 CFR 61.190 - Designation of facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... these facilities: The Feed Materials Production Center, Fernald, Ohio; the Niagara Falls Storage Site... subpart apply to the design and operation of all storage and disposal facilities for radium-containing material (i.e., byproduct material as defined under section 11.e(2) of the Atomic Energy Act of 1954...

  6. Safe design of healthcare facilities

    PubMed Central

    Reiling, J

    2006-01-01

    The physical environment has a significant impact on health and safety; however, hospitals have not been designed with the explicit goal of enhancing patient safety through facility design. In April 2002, St Joseph's Community Hospital of West Bend, a member of SynergyHealth, brought together leaders in healthcare and systems engineering to develop a set of safety‐driven facility design recommendations and principles that would guide the design of a new hospital facility focused on patient safety. By introducing safety‐driven innovations into the facility design process, environmental designers and healthcare leaders will be able to make significant contributions to patient safety. PMID:17142606

  7. Approaches to consider covers and liners in a low-level waste disposal facility performance assessment

    SciTech Connect

    Seitz, Roger; Phifer, Mark; Suttora, Linda

    2015-03-17

    On-site disposal cells are in use and being considered at several USDOE sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These disposal cells are typically regulated by States and/or the USEPA in addition to having to comply with requirements in DOE Order 435.1, Radioactive Waste Management. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. One task completed by the working group addressed approaches for considering the performance of covers and liners/leachate collection systems in the context of a performance assessment (PA). A document has been prepared which provides recommendations for a general approach to address covers and liners/leachate collection systems in a PA and how to integrate assessments with defense-in-depth considerations such as design, operations and waste acceptance criteria to address uncertainties. Specific information and references are provided for details needed to address the evolution of individual components of cover and liner/leachate collection systems. This information is then synthesized into recommendations for best practices for cover and liner system design and examples of approaches to address the performance of covers and liners as part of a performance assessment of the disposal system.

  8. Overview of a performance assessment methodology for low-level radioactive waste disposal facilities

    SciTech Connect

    Kozak, M.W.; Chu, M.S.Y.

    1991-01-01

    A performance assessment methodology has been developed for use by the US Nuclear Regulatory Commission in evaluating license applications for low-level waste disposal facilities. This paper provides a summary and an overview of the modeling approaches selected for the methodology. The overview includes discussions of the philosophy and structure of the methodology. This performance assessment methodology is designed to provide the NRC with a tool for performing confirmatory analyses in support of license reviews related to postclosure performance. The methodology allows analyses of dose to individuals from off-site releases under normal conditions as well as on-site doses to inadvertent intruders. 24 refs., 1 tab.

  9. An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities

    SciTech Connect

    Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

    2011-03-01

    Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose

  10. CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY

    SciTech Connect

    Cozzi, A.; Duncan, A.

    2010-01-28

    During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

  11. Program Plan for Revision of the Z-Area Saltstone Disposal Facility Performance Assessment

    SciTech Connect

    Cook, James R.

    2005-12-07

    Savannah River National Laboratory (SRNL) and the Saltstone Project, are embarking on the next revision to the Saltstone Disposal Facility (SDF) performance assessment (PA). This program plan has been prepared to outline the general approach, scope, schedule and resources for the PA revision. The plan briefly describes the task elements of the PA process. It discusses critical PA considerations in the development of conceptual models and interpretation of results. Applicable quality assurance (QA) requirements are identified and the methods for implementing QA for both software and documentation are described. The plan identifies project resources supporting the core team and providing project oversight. Program issues and risks are identified as well as mitigation of those risks. Finally, a preliminary program schedule has been developed and key deliverables identified. A number of significant changes have been implemented since the last PA revision resulting in a new design for future SDF disposal units. This revision will encompass the existing and planned disposal units, PA critical radionuclides and exposure pathways important to SDF performance. An integrated analysis of the overall facility layout, including all disposal units, will be performed to assess the impact of plume overlap on PA results. Finally, a rigorous treatment of uncertainty will be undertaken using probabilistic simulations. This analysis will be reviewed and approved by DOE-SR, DOE-HQ and potentially the Nuclear Regulatory Commission (NRC). This revision will be completed and ready for the start of the DOE review at the end of December 2006. This work supports a Saltstone Vault 2 fee-bearing milestone. This milestone includes completion of the Vault 2 module of the PA revision by the end of FY06.

  12. Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas

    SciTech Connect

    B. C. Rogers; P. L. Walter; R. D. Baird

    1999-08-01

    This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

  13. 49 CFR Appendix E to Part 599 - Disposal Facility Certification Form

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 7 2014-10-01 2014-10-01 false Disposal Facility Certification Form E Appendix E to Part 599 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY... CONSUMER ASSISTANCE TO RECYCLE AND SAVE ACT PROGRAM Pt. 599, App. E Appendix E to Part 599—Disposal...

  14. 49 CFR Appendix E to Part 599 - Disposal Facility Certification Form

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 7 2013-10-01 2013-10-01 false Disposal Facility Certification Form E Appendix E to Part 599 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY... CONSUMER ASSISTANCE TO RECYCLE AND SAVE ACT PROGRAM Pt. 599, App. E Appendix E to Part 599—Disposal...

  15. 49 CFR Appendix E to Part 599 - Disposal Facility Certification Form

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 7 2012-10-01 2012-10-01 false Disposal Facility Certification Form E Appendix E to Part 599 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY... CONSUMER ASSISTANCE TO RECYCLE AND SAVE ACT PROGRAM Pt. 599, App. E Appendix E to Part 599—Disposal...

  16. 49 CFR Appendix E to Part 599 - Disposal Facility Certification Form

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 7 2011-10-01 2011-10-01 false Disposal Facility Certification Form E Appendix E to Part 599 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY... CONSUMER ASSISTANCE TO RECYCLE AND SAVE ACT PROGRAM Pt. 599, App. E Appendix E to Part 599—Disposal...

  17. 40 CFR 761.213 - Use of manifest-Commercial storage and disposal facility requirements.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... AGENCY (CONTINUED) TOXIC SUBSTANCES CONTROL ACT POLYCHLORINATED BIPHENYLS (PCBs) MANUFACTURING, PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.213... or disposal facility receives PCB waste accompanied by a manifest, the owner, operator or...

  18. 40 CFR 761.213 - Use of manifest-Commercial storage and disposal facility requirements.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... AGENCY (CONTINUED) TOXIC SUBSTANCES CONTROL ACT POLYCHLORINATED BIPHENYLS (PCBs) MANUFACTURING, PROCESSING, DISTRIBUTION IN COMMERCE, AND USE PROHIBITIONS PCB Waste Disposal Records and Reports § 761.213... or disposal facility receives PCB waste accompanied by a manifest, the owner, operator or...

  19. Estimation of contaminant transport in groundwater beneath radioactive waste disposal facilities

    SciTech Connect

    Wang, J.C.; Tauxe, J.D.; Lee, D.W.

    1995-05-25

    Performance assessments are required for low-level radioactive waste disposal facilities to demonstrate compliance with the performance objectives, consider human exposures from water, air, and inadvertent intruder pathways. Among these, the groundwater pathway analysis usually involves complex numerical simulations with results which are often difficult to verify and interpret. This paper presents a technique to identify and simplify the essential parts of the groundwater analysis. The transport process of radionuclides including infiltration of precipitation, leachate generation, and advection and dispersion in the groundwater is divided into several steps. For each step, a simple analytical model is constructed and refined to capture the dominant phenomena represented in the complex analysis included in a site-specific performance assessment. This step-wise approach provides a means for gaining insights into the transport process and obtaining reasonable estimates of relevant quantities for facility design and site evaluation.

  20. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY SITE CAPSULE

    EPA Science Inventory

    In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

  1. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY - ITER

    EPA Science Inventory

    In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

  2. Ground Water Monitoring Requirements for Hazardous Waste Treatment, Storage and Disposal Facilities

    EPA Pesticide Factsheets

    The groundwater monitoring requirements for hazardous waste treatment, storage and disposal facilities (TSDFs) are just one aspect of the Resource Conservation and Recovery Act (RCRA) hazardous waste management strategy for protecting human health and the

  3. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY - ITER

    EPA Science Inventory

    In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

  4. DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY SITE CAPSULE

    EPA Science Inventory

    In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

  5. Managing commercial low-level radioactive waste beyond 1992: Transportation planning for a LLW disposal facility

    SciTech Connect

    Quinn, G.J.

    1992-01-01

    This technical bulletin presents information on the many activities and issues related to transportation of low-level radioactive waste (LLW) to allow interested States to investigate further those subjects for which proactive preparation will facilitate the development and operation of a LLW disposal facility. The activities related to transportation for a LLW disposal facility are discussed under the following headings: safety; legislation, regulations, and implementation guidance; operations-related transport (LLW and non-LLW traffic); construction traffic; economics; and public involvement.

  6. TSD-DOSE : a radiological dose assessment model for treatment, storage, and disposal facilities.

    SciTech Connect

    Pfingston, M.

    1998-12-23

    In May 1991, the U.S. Department of Energy (DOE), Office of Waste Operations, issued a nationwide moratorium on shipping slightly radioactive mixed waste from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. Studies were subsequently conducted to evaluate the radiological impacts associated with DOE's prior shipments through DOE's authorized release process under DOE Order 5400.5. To support this endeavor, a radiological assessment computer code--TSD-DOSE (Version 1.1)--was developed and issued by DOE in 1997. The code was developed on the basis of detailed radiological assessments performed for eight commercial hazardous waste TSD facilities. It was designed to utilize waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste handling operations at a TSD facility. The code has since been released for use by DOE field offices and was recently used by DOE to evaluate the release of septic waste containing residual radioactive material to a TSD facility licensed under the Resource Conservation and Recovery Act. Revisions to the code were initiated in 1997 to incorporate comments received from users and to increase TSD-DOSE's capability, accuracy, and flexibility. These updates included incorporation of the method used to estimate external radiation doses from DOE's RESRAD model and expansion of the source term to include 85 radionuclides. In addition, a detailed verification and benchmarking analysis was performed.

  7. Methodology for a consequence analysis of a nuclear waste disposal facility

    SciTech Connect

    Buchheim, B.K.; Bunschi, H.; Fitzpatrick, F.J.; Hoop, F.J.

    1983-06-01

    One of the methods currently under consideration for the disposal of radioactive wastes is emplacement in a repository within deep, continental formations. A licensing requirement for such a facility will presumably be some form of safety analysis report on the radiological impact of the facility. A methodology has been developed to make an assessment of the radiological consequences both for normal operation and for possible accident situations for a specific repository design in a salt dome at Gorleben in Germany, a repository which has been designed to accommodate all categories of radioactive waste (low, intermediate, and high level). Radionuclide release scenarios were derived from a systematic analysis of the facility design and proposed operational procedure. Where necessary, simple numerical models for such topics as direct radiation exposure from waste containers, release and transport of radionuclides, radiolysis, heat transfer, creep, and impact were developed to give a first estimate of the radiological consequences due to radionuclide releases. The results enabled sensitive areas of the design and the operational procedure to be identified, and thus possible modifications and/or precautionary measures could be recommended. The results also gave an indication of those parts of the analysis requiring more sophisticated and specialized modeling techniques to yield a more detailed radiological consequence analysis in preparation for a safety analysis report.

  8. Z-Area saltstone disposal facility groundwater monitoring report. First and second quarters 1997

    SciTech Connect

    1997-07-01

    This report presents the results of groundwater sampling during the first and second quarters of 1997 in the Z-Area Saltstone Disposal Facility. This report presents only the data for sampling during the first half of 1997 as required by industrial Solid Waste Permit No. 025500-1603. For a detailed discussion of groundwater monitoring in the Z-Area Saltstone Disposal Facility, consult the 1996 Z-Area Saltstone Disposal Annual Report. Appendix A presents the proposed South Carolina Department of Health and Environmental Control Proposed Groundwater Monitoring Standards. Flagging criteria are described in Appendix B. In May 1997 SCDHEC granted approval for seven hydrocone sampling.

  9. Groundwater Flow and Transport Calculations Supporting the Immobilized Low-Activity Waste Disposal Facility Performance Assessment

    SciTech Connect

    Bergeron, Marcel P.; Wurstner, Signe K.

    2000-12-04

    This report summarizes the Hanford Site-Wide Groundwater Model and its application to the Immobilized Low-Activity Waste (ILAW) Disposal Facility Performance Assessment (PA). The site-wide model and supporting local-scale models are used to evaluate impacts from the transport of contaminants at a hypothetical well 100 m downgradient of the disposal facilities and to evaluate regional flow conditions and transport from the ILAW disposal facilities to the Columbia River. These models were used to well-intercept factors (WIFs) or dilution factors from a given areal flux of a hypothetical contaminant released to the unconfined aquifer from the ILAW disposal facilities for two waste-disposal options: 1) a remote-handled trench concept and 2) a concrete-vault concept. The WIF is defined as the ratio of the concentration at a well location in the aquifer to the concentration of infiltrating water entering the aquifer. These WIFs are being used in conjunction with calculations of released contaminant fluxes through the vadose zone to estimate potential impacts from radiological and hazardous chemical contaminants within the ILAW disposal facility at compliance points.

  10. Book Processing Facility Design.

    ERIC Educational Resources Information Center

    Sheahan (Drake)-Stewart Dougall, Marketing and Physical Distribution Consultants, New York, NY.

    The Association of New York Libraries for Technical Services (ANYLTS) is established to develop and run a centralized book processing facility for the public library systems in New York State. ANYLTS plans to receive book orders from the 22 library systems, transmit orders to publishers, receive the volumes from the publishers, print and attach…

  11. Idaho Chemical Processing Plant Liquid Effluent Treatment and Disposal Facility hot test report

    SciTech Connect

    Hastings, R.L.

    1993-09-01

    Prior to initial operation with radioactive feed or ``hot`` operation, the Liquid Effluent Treatment and Disposal (LET&D) Facility underwent extensive testing. This report provides a detailed description and analysis of this testing. Testing has determined that LET&D is capable of processing radioactive solutions between the design flowrates of 275 gph to 550 gph. Modifications made to prevent condensation on the off-gas HEPA filters, to the process vacuum control, bottoms cooler rupture disks, and feed control system operation were successful. Unfortunately, two mixers failed prior to ``hot`` testing due to manufacturer`s error which limited operation of the PEW Evaporator System and sampling was not able to prove that design removal efficiencies for Mercury, Cadmium, Plutonium, and Non-Volatile Radionuclides.

  12. Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Boyd D. Christensen

    2012-05-01

    The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

  13. 76 FR 51879 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-19

    ... paper towel products. Operational constraints on Company H's process do not allow for reasonable... facility that further processes the industrial-sized rolls of paper into retail paper towels is not a.... Example 8. Qualified Solid Waste Disposal Facility--First Useful Product Rule--Paper Recycling. (i...

  14. Designing a Distance Learning Facility.

    ERIC Educational Resources Information Center

    Lambert, Michael P.

    1998-01-01

    Details the design of a distance-learning facility through analysis of its functions, paper-handling requirements, and current and future communications-technology needs. It also lists special features the facility should have, including up-to-date wiring capacities for telecommunications, uplink and downlink capabilities to satellites, and…

  15. Designing a Distance Learning Facility.

    ERIC Educational Resources Information Center

    Lambert, Michael P.

    1998-01-01

    Details the design of a distance-learning facility through analysis of its functions, paper-handling requirements, and current and future communications-technology needs. It also lists special features the facility should have, including up-to-date wiring capacities for telecommunications, uplink and downlink capabilities to satellites, and…

  16. Design & layout of recreation facilities

    Treesearch

    Howard R. Orr

    1971-01-01

    Design and layout of recreation facilities is a problem solving process that must be divorced from the emotionalism that has shrouded outdoor recreation and must deal deliberately with the growing information concerning people and natural resources.

  17. Experimenting with Science Facility Design.

    ERIC Educational Resources Information Center

    Butterfield, Eric

    1999-01-01

    Discusses the modern school science facility and how computers and teaching methods are changing their design. Issues include power, lighting, and space requirements; funding for planning; architect assessment; materials requirements for work surfaces; and classroom flexibility. (GR)

  18. Experimenting with Science Facility Design.

    ERIC Educational Resources Information Center

    Butterfield, Eric

    1999-01-01

    Discusses the modern school science facility and how computers and teaching methods are changing their design. Issues include power, lighting, and space requirements; funding for planning; architect assessment; materials requirements for work surfaces; and classroom flexibility. (GR)

  19. Production Facility SCADA Design Report

    SciTech Connect

    Dale, Gregory E.; Holloway, Michael Andrew; Baily, Scott A.; Woloshun, Keith Albert; Wheat, Robert Mitchell Jr.

    2015-03-23

    The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

  20. Designing Facilities for Collaborative Operations

    NASA Technical Reports Server (NTRS)

    Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

    2003-01-01

    A methodology for designing operational facilities for collaboration by multiple experts has begun to take shape as an outgrowth of a project to design such facilities for scientific operations of the planned 2003 Mars Exploration Rover (MER) mission. The methodology could also be applicable to the design of military "situation rooms" and other facilities for terrestrial missions. It was recognized in this project that modern mission operations depend heavily upon the collaborative use of computers. It was further recognized that tests have shown that layout of a facility exerts a dramatic effect on the efficiency and endurance of the operations staff. The facility designs (for example, see figure) and the methodology developed during the project reflect this recognition. One element of the methodology is a metric, called effective capacity, that was created for use in evaluating proposed MER operational facilities and may also be useful for evaluating other collaboration spaces, including meeting rooms and military situation rooms. The effective capacity of a facility is defined as the number of people in the facility who can be meaningfully engaged in its operations. A person is considered to be meaningfully engaged if the person can (1) see, hear, and communicate with everyone else present; (2) see the material under discussion (typically data on a piece of paper, computer monitor, or projection screen); and (3) provide input to the product under development by the group. The effective capacity of a facility is less than the number of people that can physically fit in the facility. For example, a typical office that contains a desktop computer has an effective capacity of .4, while a small conference room that contains a projection screen has an effective capacity of around 10. Little or no benefit would be derived from allowing the number of persons in an operational facility to exceed its effective capacity: At best, the operations staff would be underutilized

  1. Universal Design for Academic Facilities

    ERIC Educational Resources Information Center

    Salmen, John P. S.

    2011-01-01

    Universal design (UD) can play a role in many aspects of academic life and is often thought of in the context of learning. However, this chapter focuses on the impact of UD on the design of facilities in a university or campus setting. Universal design has the potential for transforming universities into truly egalitarian institutions that…

  2. Universal Design for Academic Facilities

    ERIC Educational Resources Information Center

    Salmen, John P. S.

    2011-01-01

    Universal design (UD) can play a role in many aspects of academic life and is often thought of in the context of learning. However, this chapter focuses on the impact of UD on the design of facilities in a university or campus setting. Universal design has the potential for transforming universities into truly egalitarian institutions that…

  3. Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

    SciTech Connect

    Not Available

    1988-12-01

    This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base. (TEM)

  4. Gas migration in low- and intermediate-level waste (LILW) disposal facility in Korea

    SciTech Connect

    Ha, Jae-chul; Lee, Jeong-Hwan; Jung, Haeryong; Kim, Juyub; Kim, Juyoul

    2013-07-01

    The first low- and intermediate-level waste (LILW) disposal facility is under construction in saturated granite in Korea. The safety assessment report (SAR) identified that different gases, such as hydrogen, carbon dioxide, and methane are generated at the disposal facility due to the corrosion of metal wastes and steel drum, and microbial degradation of organic matters. Reinforced concrete plays a role as an engineered barrier at the disposal facility, so its properties with regard to gas migration were evaluated in laboratory-scale experiments. Then modeling of gas migration was carried out to evaluate gas pressure build-up in the disposal facility. The gas entry pressure and relative gas permeability of the concrete was determined to be 0.97±0.15 bar, and the relative gas permeability decreased exponentially with increasing water content. The results of the modeling showed that most of hydrogen gas was dissolved in groundwater and did not significantly influence pressure build-up inside the disposal facility based on the reference case of gas generation. (authors)

  5. Corrective action management unit application for the Environmental Restoration Disposal Facility

    SciTech Connect

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ``Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.`` The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ``package`` for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package.

  6. Protocol for the E-Area Low Level Waste Facility Disposal Limits Database

    SciTech Connect

    Swingle, R

    2006-01-31

    A database has been developed to contain the disposal limits for the E-Area Low Level Waste Facility (ELLWF). This database originates in the form of an EXCEL{copyright} workbook. The pertinent sheets are translated to PDF format using Adobe ACROBAT{copyright}. The PDF version of the database is accessible from the Solid Waste Division web page on SHRINE. In addition to containing the various disposal unit limits, the database also contains hyperlinks to the original references for all limits. It is anticipated that database will be revised each time there is an addition, deletion or revision of any of the ELLWF radionuclide disposal limits.

  7. Hot cell facility design for large fusion devices

    SciTech Connect

    Barrett, R.J.; Bussell, G.T.

    1985-01-01

    Large hot cell facilities will be necessary to support the operation of large fusion devices. The supporting hot cells will be needed to serve a variety of different functions and tasks, which include reactor component maintenance, tool and maintenance equipment repair, and preparation of radioactive material for shipment and disposal. This paper discusses hot cell facility functions, requirements, and design issues and techniques. Suggested solutions and examples are given.

  8. Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility

    SciTech Connect

    Alexander, D.J.; Johnson, V.G.

    1993-09-01

    In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

  9. Radiological performance assessment for the E-Area Vaults Disposal Facility

    SciTech Connect

    Cook, J.R.

    2000-04-11

    This report is the first revision to ``Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0.

  10. 137Cs sorption into bentonite from Cidadap-Tasikmalaya as buffer material for disposal demonstration plant facility at Serpong

    NASA Astrophysics Data System (ADS)

    Setiawan, B.; Sriwahyuni, H.; Ekaningrum, NE.; Sumantry, T.

    2014-03-01

    According to co-location principle, near surface disposal type the disposal demonstration plant facility will be build at Serpong nuclear area. The facility also for anticipation of future needs to provide national facility for the servicing of radwaste management of non-nuclear power plant activity in Serpong Nuclear Area. It is needs to study the material of buffer and backfill for the safety of demonstration plant facility. A local bentonite rock from Cidadap-Tasikmalaya was used as the buffer materials. Objective of experiment is to find out the specific data of sorption characteristic of Cidadap bentonite as buffer material in a radwaste disposal system. Experiments were performed in batch method, where bentonite samples were contacted with CsCl solution labeled with Cs-137 in 100 ml/g liquid:solid ratio. Initial Cs concentration was 10-8 M and to study the effects of ionic strength and Cs concentration in solution, 0.1 and 1.0 M NaCl also CsCl concentration ranging 10-8 - 10-4 M were added in solution. As the indicator of Cs saturated in bentonite samples, Kd value was applied. Affected parameters in the experiment were contact time, effects of ionic strength and concentration of CsCl. Results showed that sorption of Cs by bentonite reached constantly after 16 days contacted, and Kd value was 10.600 ml/g. Effect of CsCl concentration on Kd value may decreased in increased in CsCl concentration. Effect of ionic strength increased according to increased in concentration of background and would effect to Kd value due to competition of Na ions and Cs in solution interacts with bentonite. By obtaining the bentonite character data as buffer material, the results could be used as the basis for making of design and the basic of performance assessment the near surface disposal facility in terms of isolation capacity of radwaste later.

  11. {sup 137}Cs sorption into bentonite from Cidadap-Tasikmalaya as buffer material for disposal demonstration plant facility at Serpong

    SciTech Connect

    Setiawan, B. Sriwahyuni, H. Ekaningrum, NE. Sumantry, T.

    2014-03-24

    According to co-location principle, near surface disposal type the disposal demonstration plant facility will be build at Serpong nuclear area. The facility also for anticipation of future needs to provide national facility for the servicing of radwaste management of non-nuclear power plant activity in Serpong Nuclear Area. It is needs to study the material of buffer and backfill for the safety of demonstration plant facility. A local bentonite rock from Cidadap-Tasikmalaya was used as the buffer materials. Objective of experiment is to find out the specific data of sorption characteristic of Cidadap bentonite as buffer material in a radwaste disposal system. Experiments were performed in batch method, where bentonite samples were contacted with CsCl solution labeled with Cs-137 in 100 ml/g liquid:solid ratio. Initial Cs concentration was 10{sup −8} M and to study the effects of ionic strength and Cs concentration in solution, 0.1 and 1.0 M NaCl also CsCl concentration ranging 10{sup −8} - 10{sup −4} M were added in solution. As the indicator of Cs saturated in bentonite samples, Kd value was applied. Affected parameters in the experiment were contact time, effects of ionic strength and concentration of CsCl. Results showed that sorption of Cs by bentonite reached constantly after 16 days contacted, and Kd value was 10.600 ml/g. Effect of CsCl concentration on Kd value may decreased in increased in CsCl concentration. Effect of ionic strength increased according to increased in concentration of background and would effect to Kd value due to competition of Na ions and Cs in solution interacts with bentonite. By obtaining the bentonite character data as buffer material, the results could be used as the basis for making of design and the basic of performance assessment the near surface disposal facility in terms of isolation capacity of radwaste later.

  12. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    SciTech Connect

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is

  13. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China.

    PubMed

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-01

    Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the

  14. Readiness assessment plan for the Radioactive Mixed Waste Land Disposal Facility (Trench 31)

    SciTech Connect

    Irons, L.G.

    1994-11-22

    This document provides the Readiness Assessment Plan (RAP) for the Project W-025 (Radioactive Mixed Waste Land Disposal Facility) Readiness Assessment (RA). The RAP documents prerequisites to be met by the operating organization prior to the RA. The RAP is to be implemented by the RA Team identified in the RAP. The RA Team is to verify the facility`s compliance with criteria identified in the RAP. The criteria are based upon the {open_quotes}Core Requirements{close_quotes} listed in DOE Order 5480.31, {open_quotes}Startup and Restart of Nuclear Facilities{close_quotes}.

  15. National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility

    SciTech Connect

    Peggy Hinman

    2010-10-01

    The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

  16. Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

    2004-09-30

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and

  17. NOMINATION FOR THE PROJECT MANAGEMENT INSTITUTE (PMI) PROJECT OF THE YEAR AWARD INTEGRATED DISPOSAL FACILITY (IDF)

    SciTech Connect

    MCLELLAN, G.W.

    2007-02-07

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal issues as well as challenges with

  18. Confined Disposal Facility at Pointe Mouillee for Detroit and Rouge Rivers.

    DTIC Science & Technology

    1974-03-01

    and Rouge Rivers at Pointe Mouillee, Michigan. The facility would also include an access channel, turning basin, mooring facility and pumpout station ...Page pI Project Description A. Great Lakes Navigation.............................. 1 B. Requirements for Dredging............... 3 C. Requirements for...Detroit River 3 1-2 Estimated Disposal Quantities 8 11-3 Water Quality for a 10-year Period at a Station 1.97 Miles Upstream from the Mouth of the Huron

  19. Audit of the deactivation, decontamination, and disposal of surplus facilities at the Savannah River Site

    SciTech Connect

    1997-10-23

    Westinghouse Savannah River Company (Westinghouse) is responsible for managing the Department of Energy`s (Department) surplus facilities at the Savannah River Site (Site). In Fiscal Year (FY) 1996, the Site had 162 surplus facilities and anticipated that 118 more would become surplus within the next 5 years. The objective of this audit was to determine whether the Savannah River Operations Office (Operations Office) and Westinghouse had economically and promptly deactivated, decontaminated, and disposed of surplus facilities at the Site. Departmental regulations require that surplus facilities be deactivated, decontaminated, and disposed of economically and promptly. However, Westinghouse only disposed of one facility and did not completely deactivate or decontaminate any of the 162 facilities identified as surplus at the Site in FY 1996. This occurred because the Operations Office did not compile a Site-wide list, establish priorities, or provide sufficient funding for the deactivation, decontamination, and disposal of surplus facilities. As a result, the Department incurred unnecessary costs for the surveillance and maintenance of surplus facilities. For example, the Department could have avoided annual costs of about $1.3 million in surveillance and maintenance costs by spending $1.2 million to perform a deactivation project on the P-Reactor process-water storage tanks. The Operations Office could have funded the project out of its unobligated FY 1996 operating funds. However, it returned the unobligated funds to the Department`s Headquarters at the end of the fiscal year. The Operations Office concurred with the finding and recommendations and initiated corrective action.

  20. Information on commercial disposal facilities that may have received offshore drilling wastes.

    SciTech Connect

    Gasper, J. R.; Veil, J. A.; Ayers, R. C., Jr.

    2000-08-25

    The U.S. Environmental Protection Agency (EPA) is developing regulations that would establish requirements for discharging synthetic-based drill cuttings from offshore wells into the ocean. Justification for allowing discharges of these cuttings is that the environmental impacts from discharging drilling wastes into the ocean may be less harmful than the impacts from hauling them to shore for disposal. In the past, some onshore commercial facilities that disposed of these cuttings were improperly managed and operated and left behind environmental problems. This report provides background information on commercial waste disposal facilities in Texas, Louisiana, California, and Alaska that received or may have received offshore drilling wastes in the past and are now undergoing cleanup.

  1. Ecological restoration and enhancement plan Mallard Ridge Recycling and Disposal Facility, Walworth County, Wisconsin

    SciTech Connect

    Leclaire, D.; Maxon, M.

    1995-12-31

    In 1988, Waste Management of Wisconsin, Inc. (WMWI) began the permitting process to expand the existing Mallard Ridge Recycling and Disposal Facility (RDF), located in Walworth County, Wisconsin. Due to the presence of several small perched wetlands and the potential presence of several state endangered and threatened reptiles, a comprehensive ecological restoration and enhancement plan was developed along with the permit application. The ecological plan addresses restoration and enhancement of natural plant communities and animal habitat for the entire 593 acre Mallard Ridge facility. The major goals of the ecological program are to create natural open space, protect and enhance the long-term ecological integrity of the site, established diverse and stable upland and wetland plant communities, and provide to protect and improve habitat for three state protected reptiles. The total amount of the site that will be vegetated with native plant communities with this plan will be about 453 acres. The plan is being conducted in phases between 1993 and 2003. This plan is designed to be a flexible one that will evolve over the years of implementation. This flexibility is necessary because the state-of-the-art of restoration and management of natural systems is constantly changing as new information, techniques, and seed sources become available. The lessons learned at this site will add to the knowledge of natural community restoration at other sites.

  2. Statistical evaluation of effluent monitoring data for the 200 Area Treated Effluent Disposal Facility

    SciTech Connect

    CJ Chou; VG Johnson

    2000-04-04

    The 200 Area Treated Effluent Disposal Facility (TEDF) consists of a pair of infiltration basins that receive wastewater originating from the 200 West and 200 East Areas of the Hanford Site. TEDF has been in operation since 1995 and is regulated by State Waste Discharge Permit ST 4502 (Ecology 1995) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216. The permit stipulates monitoring requirements for effluent (or end-of-pipe) discharges and groundwater monitoring for TEDF. Groundwater monitoring began in 1992 prior to TEDF construction. Routine effluent monitoring in accordance with the permit requirements began in late April 1995 when the facility began operations. The State Waste Discharge Permit ST 4502 included a special permit condition (S.6). This condition specified a statistical study of the variability of permitted constituents in the effluent from TEDF during its first year of operation. The study was designed to (1) demonstrate compliance with the waste discharge permit; (2) determine the variability of all constituents in the effluent that have enforcement limits, early warning values, and monitoring requirements (WHC 1995); and (3) determine if concentrations of permitted constituents vary with season. Additional and more frequent sampling was conducted for the effluent variability study. Statistical evaluation results were provided in Chou and Johnson (1996). Parts of the original first year sampling and analysis plan (WHC 1995) were continued with routine monitoring required up to the present time.

  3. Z-Area Saltstone Disposal Facility groundwater monitoring report. First and second quarters 1996

    SciTech Connect

    1996-07-01

    This report contains groundwater monitoring results from the Z-Area Saltstone Disposal Facility at the Savannah River Site. Appendix A contains the South Carolina Department of Health and Environmental Control proposed groundwater monitoring standards and final primary drinking water standards. Appendix B contains the Savannah River Site Environmental Protection Department/Environmental Monitoring Section flagging criteria for groundwater constituents.

  4. Z-Area Saltstone Disposal Facility groundwater monitoring report. 1996 annual report

    SciTech Connect

    1996-12-01

    The Z-Area Saltstone Disposal Facility is located in the Separations Area, north of H and S Areas, at the Savannah River Site (SRS). The facility permanently disposes of low-level radioactive waste. The facility blends low-level radioactive salt solution with cement, slag, and flyash to form a nonhazardous cementitious waste that is pumped to aboveground disposal vaults. Z Area began these operations in June 1990. Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed for constituents required by South Carolina Department of Health and Environmental Control (SCDHEC) Industrial Solid Waste Permit {number_sign}025500-1603 (formerly IWP-217). During second quarter 1996, lead was reported above the SCDHEC-proposed groundwater monitoring standard in one well. No other constituents were reported above SCDHEC-proposed groundwater monitoring standards for final Primary Drinking Water Standards during first, second, or third quarters 1996. Antimony was detected above SRS flagging criteria during third quarter 1996. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  5. 300 Area Treated Effluent Disposal Facility computer software release cover sheet and revision record

    SciTech Connect

    McCarthy, R.J.

    1994-11-28

    This supporting document contains the computer software release cover sheet and revision records for the 300 Area Treated Effluent Disposal Facility (TEDF). The previous revision was controlled by CH2M Hill which developed the software. A 7-page listing of the contents of directory C:{backslash}TEDF is contained in this report.

  6. Progress report on the design of a Low-Level Waste Pilot Facility at ORNL

    SciTech Connect

    Hensley, L. C.; Turner, V. L.; Pruitt, A. S.

    1980-01-01

    All low-level radioactive solid wastes, excluding TRU wastes, are disposed of by shallow land burial at the Oak Ridge National Laboratory. Contaminated liquids and sludges are hydrofractures. The TRU wastes are stored in a retrievable fashion in concrete storage facilities. Currently, the capacity for low-level radioactive waste burial at the Oak Ridge National Laboratory is adequate for another six years of service at the current solids disposal rate which ranges between 80,000 and 100,000 cu ft per year. Decontamination and decommissioning of a number of ORNL facilities will be a significant activity in the next few years. Quantities of radioactive materials to be stored or disposed of as a result of these activities will be large; therefore, the technology to dispose of large quantities of low-level radioactive wastes must be demonstrated. The UCC-ND Engineering Division, in concert with divisions of the Oak Ridge National Laboratory, has been requested to prepare a conceptual design for a facility to both dispose of the currently produced low-level radioactive waste and also to provide a test bed for demonstration of other processes which may be used in future low-level radioactive wastes disposal facilities. This facility is designated as the Low-Level Waste Pilot Facility (LLWPF). This paper describes the status of the conceptual design of a facility for disposal of the subject radioactive waste.

  7. Hazardous Waste Land Disposal Facility Assessment. Volume 2. Appendices

    DTIC Science & Technology

    1988-09-01

    Decontamination Assessment of Land and Facilities at RIA ( DALF )(RNACCPHT, 3 1984/RIC 84034R01), identified three types of potentially contaminated waste...Bibliography were reviewed. The DALF and the current Remedial Investigation/Feasibility Studies (RI/FS) of Ebasco Services Incorporated (Ebasco) and...53,000 12 119,000 -- 119,000 -- - 119,000I TOTALS L.s 65,010 AI R 6,7.6s,284.907 I )A/ DALF , 1984. 2/ Volume rounded to nearest thousand bank

  8. Vendor assessments of radioactive/mixed waste processing/disposal facilities

    SciTech Connect

    Bourassa, J.; Piscitello, T.

    1996-10-01

    This paper was developed based on Yankee Atomic Electric Company experiences gained through the performance of vendor assessments of radioactive and mixed waste processing and disposal facilities. This paper will provide insights to companies or organizations who have radioactive and/or mixed waste which requires disposal. The paper will discuss the technical, legal and programmatic issues which should be considered when evaluating waste processing and/or disposal options. The discussion focuses on the methods utilized for the preparation, performance and reporting of assessments of waste disposal vendors. The paper includes a discussion of the scope and purpose of the assessment process, and the methodologies and approach taken to evaluate the technical and programmatic areas. This paper provides guidance and direction to those individuals involved in evaluating the capabilities of the waste processing and or disposal vendors. The paper is also a resource which identifies regulatory and industry guidance available for consideration in the planning for a waste disposal/processing vendor assessment. The company needs to determine what is the most practical disposal method. This disposal method may be a combination of waste processing and direct disposal, which is consistent with the methodologies utilized by the Yankee Atomic Electric Company at the Yankee Nuclear Power Station and by other Yankee plants. Due to the anticipated/active need for utilizing a number of vendors for performing these activities, the determination has been made that assessments of the vendors supplying the services are required to ensure that activities are being effectively performed in order to minimize potential liabilities. The assessments need to consider not only the technical aspects of the operations, but also require an evaluation of the quality system(s) being utilized to ensure the consistent and effective implementation of applicable process controls.

  9. Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect

    French, Sean B.; Shuman, Rob

    2012-05-22

    of these activities cannot be used to evaluate the validity of the performance assessment and composite analysis models because the monitoring data collected are specific to operational releases or address receptors that are outside the domain of the performance assessment and composite analysis. In general, applicable monitoring data are supportive of some aspects of the performance assessment and composite analysis. Several research and development (R and D) efforts have been initiated under the performance assessment and composite analysis maintenance program. These investigations are designed to improve the current understanding of the disposal facility and site, thereby reducing the uncertainty associated with the projections of the long-term performance of Area G. The status and results of R and D activities that were undertaken in fiscal year 2011 are discussed in this report. Special analyses have been conducted to determine the feasibility of disposing of specific waste streams, to address proposed changes in disposal operations, and to consider the impacts of changes to the models used to conduct the performance assessment and composite analysis. These analyses are described and the results of the evaluations are summarized in this report. The Area G disposal facility consists of Material Disposal Area (MDA) G and the Zone 4 expansion area. To date, all disposal operations at Area G have been confined to MDA G. Material Disposal Area G is scheduled to undergo final closure in 2015; disposal of waste in the pits and shafts is scheduled to end in 2013. In anticipation of the closure of MDA G, plans are being made to ship the majority of the waste generated at LANL to off-site locations for disposal. It is not clear at this time if waste that will be disposed of at LANL will be placed in Zone 4 or if disposal operations will move to a new location at the Laboratory. Separately, efforts to optimize the final cover used in the closure of MDA G are underway; a

  10. Materials and degradation modes in an alternative LLW (low-level waste) disposal facility

    SciTech Connect

    Cowgill, M.G.; MacKenzie, D.R.

    1989-01-01

    The materials used in the construction of alternative low-level waste disposal facilities will be subject to interaction with both the internal and the external environments associated with the facilities and unless precautions are taken, may degrade, leading to structural failure. This paper reviews the characteristics of both environments with respect to three alternative disposal concepts, then assesses how reaction with them might affect the properties of the materials, which include concrete, steel-reinforced concrete, structural steel, and various protective coatings and membranes. It identifies and evaluates the probability of reactions occurring which might lead to degradation of the materials and so compromise the structure. The probability of failure (interpreted relative to the ability of the structure to restrict ingress and egress of water) is assessed for each material and precautionary measures, intended to maximize the durability of the facility, are reviewed. 19 refs., 2 tabs.

  11. ANNUAL SUMMARY OF THE INTEGRATED DISPOSAL FACILITY PERFORMANCE ASSESSMENT FOR 2004

    SciTech Connect

    MANN, F M

    2005-02-09

    As required by the US. Department of Energy (DOE) order on radioactive waste management (DOE 1999a) and as implemented by the ''Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment'' (Mann 2004), an annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a performance assessment is not issued. A draft version of the 2001 ILAW PA was sent to the DOE Headquarters (DOE/HQ) in April 2001 for review and approval. The DOE approved (DOE 2001) the draft version of the 2001 ILAW PA and issued a new version of the Hanford Site waste disposal authorization statement (DAS). Based on comments raised during the review, the draft version was revised and the 2001 ILAW PA was formally issued (Mann et al. 2001). The DOE (DOE 2003a) has reviewed the final 2001 ILAW PA and concluded that no changes to the DAS were necessary. Also as required by the DOE order, annual summaries have been generated and approved. The previous annual summary (Mann 2003b) noted the change of mission from ILAW disposal to the disposal of a range of solid waste types, including ILAW. DOE approved the annual summary (DOE 2003c), noting the expanded mission. Considering the results of data collection and analysis, the conclusions of the 2001 ILAW PA remain valid as they pertain to ILAW disposal. The new data also suggest that impacts from the disposal of the other solid waste will be lower than initially estimated in the ''Integrated Disposal Facility Risk Assessment'' (Mann 2003a). A performance assessment for the Integrated Disposal Facility (IDF) will be issued in the summer of 2005.

  12. Characterization and remediation of soil prior to construction of an on-site disposal facility at Fernald

    SciTech Connect

    Hunt, A.; Jones, G.; Janke, R.; Nelson, K.

    1998-03-01

    During the production years at the Feed Materials Production Center (FMPC), the soil of the site and the surrounding areas was surficially impacted by airborne contamination. The volume of impacted soil is estimated at 2.2 million cubic yards. During site remediation, this contamination will be excavated, characterized, and disposed of. In 1986 the US Environmental Protection Agency (EPA) and the Department of Energy (DOE) entered into a Federal Facility Compliance Agreement (FFCA) covering environmental impacts associated with the FMPC. A site wide Remedial Investigation/Feasibility Study (RI/FS) was initiated pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act (CERCLA). The DOE has completed the RI/FS process and has received approval of the final Records of Decision. The name of the facility was changed to the Fernald Environmental Management Project (FEMP) to emphasize the change in mission to environmental restoration. Remedial actions which address similar scopes of work or types of contaminated media have been grouped into remedial projects for the purpose of managing the remediation of the FEMP. The Soil Characterization and Excavation Project (SCEP) will address the remediation of FEMP soils, certain waste units, at- and below-grade material, and will certify attainment of the final remedial limits (FRLs) for the FEMP. The FEMP will be using an on-site facility for low level radioactive waste disposal. The facility will be an above-ground engineered structure constructed of geological material. The area designated for construction of the base of the on-site disposal facility (OSDF) is referred to as the footprint. Contaminated soil within the footprint must be identified and remediated. Excavation of Phase 1, the first of seven remediation areas, is complete.

  13. Application of total uncertainty theory in radioactive waste disposal facilities safety assessment

    SciTech Connect

    Lemos, Francisco Luiz de; Ross, Timothy; Sullivan, Terry

    2007-07-01

    Safety assessment requires the interaction of a large number of disciplines to model the environmental phenomena necessary to evaluate the safety of the disposal system. In this complex process, the identification and quantification of both types of uncertainties, random and epistemic, plays a very important role for confidence building. In this work an application of the concept of total uncertainty to radioactive waste disposal facilities safety assessment is proposed. By combining both types of uncertainty, aleatory and epistemic, in the same framework, this approach ultimately aims to assess the confidence one can pose in the safety-assessment decisions. (authors)

  14. EXPERIENCES FROM THE SOURCE-TERM ANALYSIS OF A LOW AND INTERMEDIATE LEVEL RADWASTE DISPOSAL FACILITY

    SciTech Connect

    Park,Jin Beak; Park, Joo-Wan; Lee, Eun-Young; Kim, Chang-Lak

    2003-02-27

    Enhancement of a computer code SAGE for evaluation of the Korean concept for a LILW waste disposal facility is discussed. Several features of source term analysis are embedded into SAGE to analyze: (1) effects of degradation mode of an engineered barrier, (2) effects of dispersion phenomena in the unsaturated zone and (3) effects of time dependent sorption coefficient in the unsaturated zone. IAEA's Vault Safety Case (VSC) approach is used to demonstrate the ability of this assessment code. Results of MASCOT are used for comparison purposes. These enhancements of the safety assessment code, SAGE, can contribute to realistic evaluation of the Korean concept of the LILW disposal project in the near future.

  15. Audits of hazardous waste TSDFs let generators sleep easy. [Hazardous waste treatment, storage and disposal facility

    SciTech Connect

    Carr, F.H.

    1990-02-01

    Because of the increasingly strict enforcement of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA), generators of hazardous waste are compelled to investigate the hazardous waste treatment, storage and disposal facility (TSDF) they use. This investigation must include an environmental and a financial audit. Simple audits may be performed by the hazardous waste generator, while more thorough ones such as those performed for groups of generators are more likely to be conducted by environmental consultants familiar with treatment, storage, and disposal techniques and the regulatory framework that guides them.

  16. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    SciTech Connect

    Reneau, S.L.; Raymond, R. Jr.

    1995-12-01

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

  17. Z-Area Saltstone Disposal Facility groundwater monitoring report. Second quarter 1995

    SciTech Connect

    1995-09-01

    The three monitoring wells at the Z-Area Saltstone Disposal Facility, ZBG 1, 1A, and 2, are sampled quarterly as part of the Savannah River Site Groundwater Monitoring Program and to comply with conditions of the facility`s Industrial Waste Permit IWP-217, issued by the South Carolina Department of Health and Environmental Control (SCDHEC). During second quarter 1995, samples from wells ZBG 1 and 2 were analyzed for selected inorganic constituents, volatile organic compounds, selected radionuclides, and other constituents. Well ZBG 1A was dry and could not be sampled. Dichloromethane, a common laboratory contaminant, was detected above final Primary Drinking Water Standards (PDWS) in well ZBG 1 and was detected in this well`s associated method blank during second quarter 1995. No other constituents exceeded final PDWS, SCDHEC proposed groundwater monitoring standards, or Savannah River Site flagging criteria in the ZBG wells during second quarter 1995. In previous quarters, wells ZBG 1 and 2 contained slightly elevated levels of tritium, similar to the tritium levels detected before Z Area began radioactive operations. The Z-Area Saltstone Disposal Facility blends low-level salt solutions with cement, slag, and flyash to form a nonhazardous cementitious waste that is pumped to aboveground disposal vaults.

  18. Orientation to pollution prevention for facility design

    SciTech Connect

    Raney, E.A.; Whitehead, J.K.; Encke, D.B.; Dorsey, J.A.

    1994-01-01

    This material was developed to assist engineers in incorporating pollution prevention into the design of new or modified facilities within the U.S. Department of Energy (DOE). The material demonstrates how the design of a facility can affect the generation of waste throughout a facility`s entire life and it offers guidance on how to prevent the generation of waste during design. Contents include: Orientation to pollution prevention for facility design training course booklet; Pollution prevention design guideline; Orientation to pollution prevention for facility design lesson plan; Training participant survey and pretest; and Training facilitator`s guide and schedule.

  19. Seismic design of industrial facilities

    NASA Astrophysics Data System (ADS)

    Arze, E.

    1993-02-01

    The design philosophy, codes, practice and experience of Chile are described and compared with other countries, mainly the USA, New Zealand and the (former) USSR. It is shown that, even though the design methods of the four countries are similar, the results in six important earthquakes since 1960 are better in Chile and the US than in New Zealand and the USSR. It is proposed that the reason for this lies in the methodology used to enforce the application of codes and specifications rather than in the design. It is finally concluded that there is a need in most countries to prepare seismic codes for industrial facilities and structures and to stress in them the requirements for compulsory design review and construction inspection.

  20. Lessons Learned from the On-Site Disposal Facility at Fernald Closure Project

    SciTech Connect

    Kumthekar, U.A.; Chiou, J.D.

    2006-07-01

    The On-Site Disposal Facility (OSDF) at the U.S. Department of Energy's (DOE) Fernald Closure Project near Cincinnati, Ohio is an engineered above-grade waste disposal facility being constructed to permanently store low level radioactive waste (LLRW) and treated mixed LLRW generated during Decommissioning and Demolition (D and D) and soil remediation performed in order to achieve the final land use goal at the site. The OSDF is engineered to store 2.93 million cubic yards of waste derived from the remediation activities. The OSDF is intended to isolate its LLRW from the environment for at least 200 years and for up to 1,000 years to the extent practicable and achievable. Construction of the OSDF started in 1997 and waste placement activities will complete by the middle of April 2006 with the final cover (cap) placement over the last open cell by the end of Spring 2006. An on-site disposal alternative is considered critical to the success of many large-scale DOE remediation projects throughout the United States. However, for various reasons this cost effective alternative is not readily available in many cases. Over the last ten years Fluor Fernald Inc. has cumulated many valuable lessons learned through the complex engineering, construction, operation, and closure processes of the OSDF. Also in the last several years representatives from other DOE sites, State agencies, as well as foreign government agencies have visited the Fernald site to look for proven experiences and practices, which may be adapted for their sites. This paper present a summary of the major issues and lessons leaned at the Fernald site related to engineering, construction, operation, and closure processes for the disposal of remediation waste. The purpose of this paper is to share lessons learned and to benefit other projects considering or operating similar on-site disposal facilities from our successful experiences. (authors)

  1. State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site

    SciTech Connect

    Not Available

    1993-08-01

    Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

  2. PORFLOW Simulations Supporting Saltstone Disposal Unit Design Optimization

    SciTech Connect

    Flach, G. P.; Hang, T.; Taylor, G. A.

    2015-12-10

    SRNL was requested by SRR to perform PORFLOW simulations to support potential cost-saving design modifications to future Saltstone Disposal Units in Z-Area (SRR-CWDA-2015-00120). The design sensitivity cases are defined in a modeling input specification document SRR-CWDA-2015-00133 Rev. 1. A high-level description of PORFLOW modeling and interpretation of results are provided in SRR-CWDA-2015-00169. The present report focuses on underlying technical issues and details of PORFLOW modeling not addressed by the input specification and results interpretation documents. Design checking of PORFLOW modeling is documented in SRNL-L3200-2015-00146.

  3. Radiological performance assessment for the Z-Area Saltstone Disposal Facility

    SciTech Connect

    Cook, J.R.; Fowler, J.R.

    1992-12-18

    This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

  4. Dose consequences from a postulated criticality occurring in a low-level waste disposal facility

    SciTech Connect

    Broadhead, B.L.; Childs, R.L.; Hopper, C.M.; Parks, C.V.

    1997-12-01

    Evaluations were done to determine conditions that could permit nuclear criticality with fissile uranium in low-level waste (LLW) facilities and to estimate potential radiation exposures to personnel if there were such an accident. Simultaneous hydrogeochemical and nuclear criticality studies were done (1) to identity realistic scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) to model groundwater transport of uranium and subsequent concentration via sorption or precipitation, (3) to evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits, and (4) to estimate potential radiation exposures to personnel resulting from criticality consequences. This paper presents the details of the radiation exposure calculations relying on the conditions as determined from the preceding studies detailed in a cited reference.

  5. Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.

    SciTech Connect

    Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt)

    2003-10-01

    A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron

  6. Aboveground roofed design for the disposal of low-level radioactive waste in Maine

    SciTech Connect

    Alexander, J.A.

    1993-03-01

    The conceptual designs proposed in this report resulted from a study for the Maine Low-level Radioactive Waste Authority to develop conceptual designs for a safe and reliable disposal facility for Maine`s low-level radioactive waste (LLW). Freezing temperatures, heavy rainfall, high groundwater tables, and very complex and shallow glaciated soils found in Maine place severe constraints on the design. The fundamental idea behind the study was to consider Maine`s climatic and geological conditions at the beginning of conceptual design rather than starting with a design for another location and adapting it for Maine`s conditions. The conceptual designs recommended are entirely above ground and consist of an inner vault designed to provide shielding and protection against inadvertent intrusion and an outer building to protect the inner vault from water. The air dry conditions within the outer building should lead to almost indefinite service life for the concrete inner vault and the waste containers. This concept differs sharply from the usual aboveground vault in its reliance on at least two independent, but more or less conventional, roofing systems for primary and secondary protection against leakage of radioisotopes from the facility. Features include disposal of waste in air dry environment, waste loading and visual inspection by remote-controlled overhead cranes, and reliance on engineered soils for tertiary protection against release of radioactive materials.

  7. Interpretation and Modelling of Data from Site Investigations for a Geological Disposal facility located in the UK

    NASA Astrophysics Data System (ADS)

    Clark, H.; Bailey, L.; Parkes, A.

    2012-04-01

    The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal in the United Kingdom. The implementation process envisaged is that once a candidate site or sites for a geological disposal facility have been identified, NDA-RWMD will undertake surface-based investigations at the site or sites. The information acquired through these investigations would be used as an input to the development of the safety case, for engineering design of the disposal facility and to demonstrate confidence to the key stakeholders that the potential disposal facility site is adequately understood. NDA-RWMD proposes to develop and present the information derived from site characterisation activities in the form of a single integrated Site Descriptive Model, i.e. a description of the geometry, properties of the bedrock and water, and the associated interacting processes and mechanisms, which will be used to address the information requirements of all the end users (including the safety case). It is anticipated that, in a similar way to the approach adopted by international radioactive waste programmes led by SKB (Sweden) and Posiva (Finland), the integrated Site Descriptive Model will be divided into parts comprising clearly defined disciplines which may form either chapters or discipline-based models such as: • Geology; • Hydrogeology; • Hydrochemistry; • Geotechnical; • Radionuclide Transport Properties; • Thermal Properties; and • Biosphere. The integrated Site Descriptive Model will evolve as understanding of the particular site advances and will describe the current understanding of a specific site and, where relevant, the historical development of conditions at the site where this supports the conceptual understanding. The Site Descriptive Model will not include prediction of the future evolution of the conditions at the site: this will be an important component

  8. Absorbent Analysis of Anniston Chemical Agent Disposal Facility Munition Demilitarization Building (MDB) Banks 1 and 2 Filter Samples Following Completion of The GB Agent and VX Rocket Campaigns

    DTIC Science & Technology

    2013-01-01

    ADSORBENT ANALYSIS OF ANNISTON CHEMICAL AGENT DISPOSAL FACILITY MUNITION...DATES COVERED (From - To) March 2007 – July 2007 4. TITLE AND SUBTITLE Adsorbent Analysis of Anniston Chemical Agent Disposal Facility Munition...Building (MDB) Banks 1 and 2 ventilation filters from the Anniston Chemical Agent Disposal Facility were analyzed for the level of GB and VX

  9. Z-Area Saltstone Disposal Facility Groundwater Monitoring Report. 1997 Annual Report

    SciTech Connect

    Roach, J.L. Jr.

    1997-12-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed for constituents required by South Carolina Department of Health and Environmental Control (SCDHEC) Industrial Solid Waste Permit {number_sign}025500-1603 (formerly IWP-217). No constituents were reported above SCDHEC-proposed groundwater monitoring standards or final Primary Drinking Water Standards during first or third quareters 1997. No constituents were detected above SRS flagging criteria during first or third quarters 1997.

  10. Statistical Evaluation of Effluent Monitoring Data for the 200 Area Treated Effluent Disposal Facility

    SciTech Connect

    Chou, Charissa J.; Johnson, Vernon G.

    2000-03-08

    This report updates the original effluent variability study for the 200 Area Treated Effluent Disposal Facility (TEDF) and provides supporting justification for modifying the effluent monitoring portion of the discharge permit. Four years of monitoring data were evaluated and used to statistically justify changes in permit effluent monitoring conditions. As a result, the TEDF effluent composition and variability of the effluent waste stream are now well defined.

  11. 200 Area Treated Effluent Disposal Facility (TEDF) Effluent Sampling and Analysis Plan

    SciTech Connect

    BROWN, M.J.

    2000-05-18

    This Sampling and Analysis Plan (SAP) has been developed to comply with effluent monitoring requirements at the 200 Area Treated Effluent Disposal Facility (TEDF), as stated in Washington State Waste Discharge Permit No. ST 4502 (Ecology 2000). This permit, issued by the Washington State Department of Ecology (Ecology) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216, is an April 2000 renewal of the original permit issued on April 1995.

  12. ENGINEERED NEAR SURFACE DISPOSAL FACILITY OF THE INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT AT CHERNOBYL NUCLEAR POWER PLANT

    SciTech Connect

    Ziehm, Ronny; Pichurin, Sergey Grigorevich

    2003-02-27

    As a part of the turnkey project ''Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant (ChNPP)'' an Engineered Near Surface Disposal Facility (ENSDF, LOT 3) will be built on the VEKTOR site within the 30 km Exclusion Zone of the ChNPP. This will be performed by RWE NUKEM GmbH, Germany, and it governs the design, licensing support, fabrication, assembly, testing, inspection, delivery, erection, installation and commissioning of the ENSDF. The ENSDF will receive low to intermediate level, short lived, processed/conditioned wastes from the ICSRM Solid Waste Processing Facility (SWPF, LOT 2), the ChNPP Liquid Radwaste Treatment Plant (LRTP) and the ChNPP Interim Storage Facility for RBMK Fuel Assemblies (ISF). The ENSDF has a capacity of 55,000 m{sup 3}. The primary functions of the ENSDF are: to receive, monitor and record waste packages, to load the waste packages into concrete disposal units, to enable capping and closure of the disposal unit s, to allow monitoring following closure. The ENSDF comprises the turnkey installation of a near surface repository in the form of an engineered facility for the final disposal of LILW-SL conditioned in the ICSRM SWPF and other sources of Chernobyl waste. The project has to deal with the challenges of the Chernobyl environment, the fulfillment of both Western and Ukrainian standards, and the installation and coordination of an international project team. It will be shown that proven technologies and processes can be assembled into a unique Management Concept dealing with all the necessary demands and requirements of a turnkey project. The paper emphasizes the proposed concepts for the ENSDF and their integration into existing infrastructure and installations of the VEKTOR site. Further, the paper will consider the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian

  13. Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

    2012-05-01

    This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

  14. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    SciTech Connect

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

  15. 10 CFR 61.51 - Disposal site design for land disposal.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... extent practicable water infiltration, to direct percolating or surface water away from the disposed... must direct surface water drainage away from disposal units at velocities and gradients which will not result in erosion that will require ongoing active maintenance in the future. (6) The disposal site...

  16. 78 FR 37759 - Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-24

    ... AGENCY 40 CFR Part 228 Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation... designate the Atchafalaya-West Ocean Dredged Material Disposal Site pursuant to the draft EIS, ``Designation of the Atchafalaya River Bar Channel Ocean Dredged Material Disposal Site Pursuant to Section 102(c...

  17. 49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not... the drive train (unless with respect to the drive train, the transmission, drive shaft, and rear...

  18. 49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not... the drive train (unless with respect to the drive train, the transmission, drive shaft, and rear...

  19. 49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not... the drive train (unless with respect to the drive train, the transmission, drive shaft, and rear...

  20. 49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not... the drive train (unless with respect to the drive train, the transmission, drive shaft, and rear...

  1. 49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not... the drive train (unless with respect to the drive train, the transmission, drive shaft, and rear...

  2. Engineering test facility design definition

    NASA Technical Reports Server (NTRS)

    Bercaw, R. W.; Seikel, G. R.

    1980-01-01

    The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

  3. National Ignition Facility system design requirements conventional facilities SDR001

    SciTech Connect

    Hands, J.

    1996-04-09

    This System Design Requirements (SDR) document specifies the functions to be performed and the minimum design requirements for the National Ignition Facility (NIF) site infrastructure and conventional facilities. These consist of the physical site and buildings necessary to house the laser, target chamber, target preparation areas, optics support and ancillary functions.

  4. PORFLOW MODELING FOR A PRELIMINARY ASSESSMENT OF THE PERFORMANCE OF NEW SALTSTONE DISPOSAL UNIT DESIGNS

    SciTech Connect

    Smith, F.

    2012-08-06

    At the request of Savannah River Remediation (SRR), SRNL has analyzed the expected performance obtained from using seven 32 million gallon Saltstone Disposal Units (SDUs) in the Z-Area Saltstone Disposal Facility (SDF) to store future saltstone grout. The analysis was based on preliminary SDU final design specifications. The analysis used PORFLOW modeling to calculate the release of 20 radionuclides from an SDU and transport of the radionuclides and daughters through the vadose zone. Results from this vadose zone analysis were combined with previously calculated releases from existing saltstone vaults and FDCs and a second PORFLOW model run to calculate aquifer transport to assessment points located along a boundary 100 m from the nearest edge of the SDF sources. Peak concentrations within 12 sectors spaced along the 100 m boundary were determined over a period of evaluation extending 20,000 years after SDF closure cap placement. These peak concentrations were provided to SRR to use as input for dose calculations.

  5. Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011

    SciTech Connect

    French, Sean B.; Shuman, Robert

    2012-04-17

    The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call

  6. Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site

    SciTech Connect

    Baer, T.A.; Emery, J.N.; Price, L.L.; Olague, N.E.

    1994-04-01

    The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

  7. Z-Area Saltstone Disposal Facility groundwater monitoring report. First quarter 1995

    SciTech Connect

    1995-06-01

    The three monitoring wells at the Z-Area Saltstone Disposal Facility, ZBG 1, 1A, and 2, are sampled quarterly as part of the Savannah River Site Groundwater Monitoring Program and to comply with conditions of the facility`s Industrial Waste Permit IWP-217, issued by the South Carolina Department of Health and Environmental Control (SCDHEC). During first quarter 1995, samples from wells ZBG 1 and 2 were analyzed for selected inorganic constituents, volatile organic compounds, selected radionuclides, and other constituents. Well ZBG 1A was dry and could not be sampled. None of the wells contained constituents above SCDHEC proposed groundwater monitoring standards, final Primary Drinking Water Standards, or flagging criteria. In previous quarters, wells ZBG 1 and 2 contained slightly elevated levels of tritium, similar to the tritium levels detected before Z Area began radioactive operations.

  8. Steam plant ash disposal facility and industrial landfill at the Y-12 Plant, Anderson County, Tennessee

    SciTech Connect

    Not Available

    1992-02-01

    The US Department of Energy (DOE) is proposing to install a wet ash handling system to dewater bottom ash from the coal-fired steam plant at its Y-12 Plant and to construct a new landfill for disposal of industrial wastes, including the dewatered bottom ash. The DOE operates three major facilities on its Oak Ridge Reservation (ORR). Operation of these facilities results in the production of a variety of nonhazardous, nonradioactive solid wastes (approximately 300 m{sup 3} per day, compacted) including sanitary wastes, common industrial wastes and construction debris. At the current rate of use, this existing landfill will be filled within approximately 18 months, and more space is urgently needed. In an effort to alleviate this problem, DOE and WMD management propose to create additional landfill facilities at a nearby site. The potential environmental impacts associated with this proposed action are the subject of this environmental assessment (EA).

  9. Laboratory Animal Facilities. Laboratory Design Notes.

    ERIC Educational Resources Information Center

    Jonas, Albert M.

    1965-01-01

    Design of laboratory animal facilities must be functional. Accordingly, the designer should be aware of the complex nature of animal research and specifically the type of animal research which will be conducted in a new facility. The building of animal-care facilities in research institutions requires special knowledge in laboratory animal…

  10. LEACHATE MIGRATION FROM A SOLID WASTE DISPOSAL FACILITY NEAR BISCAYNE NATIONAL PARK, SOUTH FLORIDA.

    USGS Publications Warehouse

    Waller, Bradley G.; Labowski, James L.

    1987-01-01

    Leachate from the Dade County Solid Waste Disposal Facility (SWDF) is migrating to the east (seaward) and to the south from the currently active disposal cell. Water levels and ground-water flow directions are strongly influenced by water-management practices. The SWDF is constructed over the salt-intruded part of the highly transmissive Biscayne aquifer and because of this, chloride ion concentrations and specific conductance levels could not be used as indicators of leachate concentrations. Leachate was detected in multi-depth wells located 75 meters to the south and 20 meters to the east of the active cell. Concentrations of water-quality indicators had mean concentrations generally 2 to 10 times higher than baseline conditions. Primary controls over leachate movement in the SWDF are water-management practices in the Black Creek and Gould Canals, configuration and integrity of the liner beneath the active cell, and low hydraulic gradients in the landfill area.

  11. ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

    SciTech Connect

    Phillips, Ann Marie; Meservey, Richard H.

    2003-02-27

    Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

  12. Technical site characterization of the Mercer County Ash Disposal Facility: A case history

    SciTech Connect

    Allen, R.C.; Walton, C.G.; Zweig, L.T. )

    1993-03-01

    The Waste-Tech Services, Inc., Mercer County Ash Disposal Facility is a proposed Resource Conservation and Recovery Act (RCRA) permitted hazardous waste treatment, storage and disposal facility located SW of Princeton, Missouri. The facility is to accept, store, treat and landfill ash residues from RCRA-permitted hazardous waste incineration. The site was characterized for a permit application submitted to the Missouri Department of Natural Resource (MDNR). MDNR was involved during all site characterization stages, including MDNR review, input and oversight during the planning, field execution and report-preparation stages. Both parties agreed upon the needs required for characterizing the sites prior field work, and the MDNR ensured that scope of work stipulations were implemented in the field and reported. Three broad characterization categories were defined: (1) physical characteristics; (2) biological characteristics; and, (3) socio-economic considerations. Physical criteria include the geologic, geotechnical, hydrogeologic and hydrologic site conditions. Threatened and Endangered Species and Wetlands comprised the biologic issues. Socio-economics considered cultural resources, such as history and archeology, market proximity, capacity assurance and transportation.

  13. The contractor`s role in low-level waste disposal facility application review and licensing

    SciTech Connect

    Serie, P.J.; Dressen, A.L.

    1991-12-31

    The California Department of Health Services will soon reach a licensing decision on the proposed Ward Valley low-level radioactive waste disposal facility. As the first regulatory agency in the country to address the 10 CFR Part 61 requirements for a new disposal facility, California`s program has broken new ground in its approach. Throughout the review process, the Department has relied on contractor support to augment its technical and administrative staff. A team consisting of Roy F. Weston, Inc., supported by ERM-Program Management Corp., Environmental Issues Management, Inc., and Rogers and Associates Engineering Corporation, has worked closely with the Department in a staff extension role. The authors have been involved with the project in contractor project management roles since 1987, and continue to support the Department`s program as it proceeds to finalize its licensing process. This paper describes the selection process used to identify a contractor team with the needed skills and experience, and the makeup of team capabilities. It outlines the management, communication, and technical approaches used to assure a smooth agency-contractor function and relationship. It describes the techniques used to ensure that decisions and documents represented the Department credibly in its role as the regulatory and licensing agency under the Nuclear Regulatory Commission (NRC) Agreement State program. The paper outlines the license application review process and activities, through preparation of licensing documentation and responses to public comments. Lessons learned in coordination of an agency-contractor team effort to review and license a low-level waste disposal facility are reviewed and suggestions made for approaching a similar license application review and licensing situation.

  14. Z-Area Saltstone Disposal Facility groundwater monitoring report, Fourth quarter 1995 and 1995 summary

    SciTech Connect

    Coward, L.S.

    1996-03-01

    Samples from the ZBG wells at the Z-Area Saltstone Disposal Facility are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Industrial Waster Permit IWP-217 and for other constituents as part of the Savannah River Site Groundwater Monitoring Program. During fourth quarter 1995, no constituents were reported above final Primary Drinking Water Standards or SRS flagging criteria. In the past, tritium has been detected sporadically in the ZBG wells at levels similar to those detected before Z Area began radioactive operations.

  15. Integrated disposal Facility Sagebrush Habitat Mitigation Project: FY2007 Compensation Area Monitoring Report

    SciTech Connect

    Durham, Robin E.; Sackschewsky, Michael R.

    2007-09-01

    This report summarizes the first year survival of sagebrush seedlings planted as compensatory mitigation for the Integrated Disposal Facility Project. Approximately 42,600 bare root seedlings and 26,000 pluglings were planted at a mitigation site along Army Loop Road in February 2007. Initial baseline monitoring occurred in March 2007, and first summer survival was assessed in September 2007. Overall survival was 19%, with bare root survival being marginally better than pluglings (21% versus 14%). Likely major factors contributing to low survival were late season planting and insufficient soil moisture during seedling establishment.

  16. Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

    SciTech Connect

    Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

    1994-08-01

    This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

  17. Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. Erratum

    SciTech Connect

    Smith, Gary L.

    2016-09-06

    This report refers to or contains Kg values for glasses LAWA44, LAWB45 and LAWC22 affected by calculations errors as identified by Papathanassiu et al. (2011). The corrected Kg values are reported in an erratum included in the revised version of the original report. The revised report can be referenced as follows: Pierce E. M. et al. (2004) Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. PNNL-14805 Rev. 0 Erratum. Pacific Northwest National Laboratory, Richland, WA, USA.

  18. Waste Form Release Calculations for the 2005 Integrated Disposal Facility Performance Assessment. Erratum

    SciTech Connect

    Smith, Gary L.

    2016-09-06

    This report refers to or contains Kg values for glasses LAWA44, LAWB45 and LAWC22 affected by calculations errors as identified by Papathanassiu et al. (2011). The corrected Kg values are reported in an erratum included in the revised version of the original report. The revised report can be referenced as follows: Pierce E. M. et al. (2004) Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. PNNL-14805 Rev. 0 Erratum. Pacific Northwest National Laboratory, Richland, WA, USA.

  19. Preliminary geotechnical evaluation of deep borehole facilities for nuclear waste disposal in shales

    SciTech Connect

    Nataraj, M.S. New Orleans Univ., LA . Dept. of Civil Engineering)

    1991-01-01

    This study is concerned with a preliminary engineering evaluation of borehole facilities for nuclear waste disposal in shales. Some of the geotechnical properties of Pierre, Rhinestreet, and typical illite shale have been collected. The influence of a few geotechnical properties on strength and deformation of host material is briefly examined. It appears that Pierre shale is very unstable and requires support to prevent collapse. Typical illite shale is more stable than Rhinestreet shale, although it undergoes relatively more deformation. 16 refs., 5 figs., 3 tabs.

  20. Nuclear criticality safety assessment of the low level radioactive waste disposal facility trenches

    SciTech Connect

    Kahook, S.D.

    1994-04-01

    Results of the analyses performed to evaluate the possibility of nuclear criticality in the Low Level Radioactive Waste Disposal Facility (LLRWDF) trenches are documented in this report. The studies presented in this document are limited to assessment of the possibility of criticality due to existing conditions in the LLRWDF. This document does not propose nor set limits for enriched uranium (EU) burial in the LLRWDF and is not a nuclear criticality safety evaluation nor analysis. The calculations presented in the report are Level 2 calculations as defined by the E7 Procedure 2.31, Engineering Calculations.

  1. A process for establishing a financial assurance plan for LLW disposal facilities

    SciTech Connect

    Smith, P.

    1993-04-01

    This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided.

  2. Cold vacuum drying facility design requirements

    SciTech Connect

    Irwin, J.J.

    1997-09-24

    This release of the Design Requirements Document is a complete restructuring and rewrite to the document previously prepared and released for project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility.

  3. PROCESS DESIGN MANUAL FOR SLUDGE TREATMENT AND DISPOSAL

    EPA Science Inventory

    The purpose of this manual is to provide the engineering community and related industry with a new source of information to be used in the planning, design, and operation of present and future wastewater pollution control facilities. This manual supplements this existing knowledg...

  4. PROCESS DESIGN MANUAL FOR SLUDGE TREATMENT AND DISPOSAL

    EPA Science Inventory

    The purpose of this manual is to provide the engineering community and related industry with a new source of information to be used in the planning, design, and operation of present and future wastewater pollution control facilities. This manual supplements this existing knowledg...

  5. The Site Investigation Of Low-Level Radioactive Waste For Sub-Surface Disposal Facility In Japan

    NASA Astrophysics Data System (ADS)

    Hosoya, S.; Sasaki, T.

    2006-12-01

    [1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short "the sub-surface disposal facility".This facility can accept the relatively higher low-level waste from unclear power plant operation and in core materials from the decommissioning, estimated about 20 thousands cubic meter in total.In addition, this will accept transuranim (TRU) slightly contaminated waste from reprocessing plant operation and decommissioning. It shall be located at a sufficient depth enough to avoid normal human activities in future. [2.Site investigation] From 2001 to 2006,the site investigation on geology and hydrogeology has been performed in order to acquire the basic data for the design and the safety assessment for the sub-surface disposal facility.The candidate area is located at the site of JNFL, where Rokkasho-mura, Aomori Prefecture in the northern area of the Mainland of Japan.To confirm geology hydraulic conditions and geo-chemistry, 22 boring survey including 6 holes in swamp and marsh have been performed. The 1km long access tunnel (the entrance level EL 8.0m, incline of 1/10) to the altitude of EL -86m underground, around 100m depth from surface, has excavated. During excavating the tunnel, observation of geology, permeability tests, pore water pressure measurements and so on has been performed in situ.And the large size test cavern of 18m diameters was constructed at the end of the tunnel to demonstrate stability of the tunnel. Prior to the excavation, 3 measuring tunnels were excavated surrounding the test cavern to examine the excavation. [3.Geological features] The sedimentary rock called Takahoko formation at the Neogene period is distributed upper than EL-500m in the candidate area.The quaternary stratum about 10m in thickness is

  6. Long-term criticality control in radioactive waste disposal facilities using depleted uranium

    SciTech Connect

    Forsberg, C.W.

    1997-02-19

    Plant photosynthesis has created a unique planetary-wide geochemistry - an oxidizing atmosphere with oxidizing surface waters on a planetary body with chemically reducing conditions near or at some distance below the surface. Uranium is four orders of magnitude more soluble under chemically oxidizing conditions than it is under chemically reducing conditions. Thus, uranium tends to leach from surface rock and disposal sites, move with groundwater, and concentrate where chemically reducing conditions appear. Earth`s geochemistry concentrates uranium and can separate uranium from all other elements except oxygen, hydrogen (in water), and silicon (silicates, etc). Fissile isotopes include {sup 235}U, {sup 233}U, and many higher actinides that eventually decay to one of these two uranium isotopes. The potential for nuclear criticality exists if the precipitated uranium from disposal sites has a significant fissile enrichment, mass, and volume. The earth`s geochemistry suggests that isotopic dilution of fissile materials in waste with {sup 238}U is a preferred strategy to prevent long-term nuclear criticality in and beyond the boundaries of waste disposal facilities because the {sup 238}U does not separate from the fissile uranium isotopes. Geological, laboratory, and theoretical data indicate that the potential for nuclear criticality can be minimized by diluting fissile materials with-{sup 238}U to 1 wt % {sup 235}U equivalent.

  7. Secondary Waste Cementitious Waste Form Data Package for the Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Cantrell, Kirk J.; Westsik, Joseph H.; Serne, R Jeffrey; Um, Wooyong; Cozzi, Alex D.

    2016-05-16

    A review of the most up-to-date and relevant data currently available was conducted to develop a set of recommended values for use in the Integrated Disposal Facility (IDF) performance assessment (PA) to model contaminant release from a cementitious waste form for aqueous wastes treated at the Hanford Effluent Treatment Facility (ETF). This data package relies primarily upon recent data collected on Cast Stone formulations fabricated with simulants of low-activity waste (LAW) and liquid secondary wastes expected to be produced at Hanford. These data were supplemented, when necessary, with data developed for saltstone (a similar grout waste form used at the Savannah River Site). Work is currently underway to collect data on cementitious waste forms that are similar to Cast Stone and saltstone but are tailored to the characteristics of ETF-treated liquid secondary wastes. Recommended values for key parameters to conduct PA modeling of contaminant release from ETF-treated liquid waste are provided.

  8. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2012-08-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  9. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2009-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  10. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2010-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  11. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2012-04-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  12. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Gary Mecham

    2010-05-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  13. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  14. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    SciTech Connect

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the

  15. Cold vacuum drying facility design requirements

    SciTech Connect

    IRWIN, J.J.

    1999-07-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  16. Approach to the vadose zone monitoring in hazardous and solid waste disposal facilities

    NASA Astrophysics Data System (ADS)

    Twardowska, Irena

    2004-03-01

    In the solid waste (SW)disposal sites, in particular at the unlined facilities, at the remediated or newly-constructed units equipped with novel protective/reactive permeable barriers or at lined facilities with leachate collection systems that are prone to failure, the vadose zone monitoring should comprise besides the natural soil layer beneath the landfill, also the anthropogenic vadose zone, i.e. the waste layer and pore solutions in the landfill. The vadose zone screening along the vertical profile of SW facilities with use of direct invasive soil-core and soil-pore liquid techniques shows vertical downward redistribution of inorganic (macroconstituents and heavy metals) and organic (PAHs) contaminant loads in water infiltrating through the waste layer. These loads can make ground water down-gradient of the dump unfit for any use. To avoid damage of protective/reactive permeable barriers and liners, an installation of stationary monitoring systems along the waste layer profile during the construction of a landfill, which are amenable to generate accurate data and information in a near-real time should be considered including:(i) permanent samplers of pore solution, with a periodic pump-induced transport of collected solution to the surface, preferably with instant field measurements;(ii)chemical sensors with continuous registration of critical parameters. These techniques would definitely provide an early alert in case when the chemical composition of pore solution percolating downward the waste profile shows unfavorable transformations, which indicate an excessive contaminant load approaching ground water. The problems concerning invasive and stationary monitoring of the vadose zone in SW disposal facilities will be discussed at the background of results of monitoring data and properties of permeable protective/reactive barriers considered for use.

  17. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    SciTech Connect

    Smith, Frank G.; Phifer, Mark A.

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory

  18. The Vapor Plume at Material Disposal Are C in Relation to Pajarito Corridor Facilities

    SciTech Connect

    Masse, William B.

    2012-04-02

    A vapor plume made up of volatile organic compounds is present beneath Material Disposal Area C (MDA C) at Los Alamos National Laboratory (LANL). The location and concentrations within the vapor plume are discussed in relation to existing and planned facilities and construction activities along Pajarito Road (the 'Pajarito Corridor') and in terms of worker health and safety. This document provides information that indicates that the vapor plume does not pose a threat to the health of LANL workers nor will it pose a threat to workers during construction of proposed facilities along Pajarito Road. The Los Alamos National Laboratory (LANL or the Laboratory) monitors emissions, effluents, and environmental media to meet environmental compliance requirements, determine actions to protect the environment, and monitor the long-term health of the local environment. LANL also studies and characterizes 'legacy' waste from past Laboratory operations to make informed decisions regarding eventual corrective actions and the disposition of that waste. Starting in 1969, these activities have been annually reported in the LANL Environmental Report (formerly Environmental Surveillance Report), and are detailed in publicly accessible technical reports meeting environmental compliance requirements. Included among the legacy sites being investigated are several formerly used material disposal areas (MDAs) set aside by the Laboratory for the general on-site disposal of waste from mission-related activities. One such area is MDA C located in Technical Area 50 (TA-50), which was used for waste disposal between 1948 and 1974. The location of TA-50 is depicted in Figure 1. The present paper uses a series of maps and cross sections to address the public concerns raised about the vapor plume at MDA C. As illustrated here, extensive sampling and data interpretation indicate that the vapor plume at MDA C does not pose a threat to the health of LANL workers nor will it pose a threat to workers

  19. Planning and Designing Safe Facilities

    ERIC Educational Resources Information Center

    Seidler, Todd

    2006-01-01

    Those who manage physical education, athletic, and recreation programs have a number of legal duties that they are expected to carry out. Among these are an obligation to take reasonable precautions to ensure safe programs and facilities for all participants, spectators, and staff. Physical education and sports facilities that are poorly planned,…

  20. An Updated Performance Assessment For A New Low-Level Radioactive Waste Disposal Facility In West Texas - 12192

    SciTech Connect

    Dornsife, William P.; Kirk, J. Scott; Shaw, Chris G.

    2012-07-01

    This Performance Assessment (PA) submittal is an update to the original PA that was developed to support the licensing of the Waste Control Specialists LLC Low-Level Radioactive Waste (LLRW) disposal facility. This update includes both the Compact Waste Facility (CWF) and the Federal Waste Facility (FWF), in accordance with Radioactive Material License (RML) No. R04100, License Condition (LC) 87. While many of the baseline assumptions supporting the initial license application PA were incorporated in this update, a new transport code, GoldSim, and new deterministic groundwater flow codes, including HYDRUS and MODFLOWSURFACT{sup TM}, were employed to demonstrate compliance with the performance objectives codified in the regulations and RML No. R04100, LC 87. A revised source term, provided by the Texas Commission on Environmental Quality staff, was used to match the initial 15 year license term. This updated PA clearly confirms and demonstrates the robustness of the characteristics of the site's geology and the advanced engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public and site workers predicted in the initial and updated PA were a small fraction of the criterion doses of 0.25 mSv and 50 mSv, respectively. In a comparison between the results of the updated PA against the one developed in support of the initial license, both clearly demonstrated the robustness of the characteristics of the site's geology and engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public predicted in the initial and updated PA were a fraction of the allowable 25 mrem/yr (0.25 m sievert/yr) dose standard for tens-of-thousands of years into the future. Draft Texas guidance on performance assessment (TCEQ, 2004) recommends a period of analysis equal to 1,000 years or until peak doses from the more

  1. Applying 3D Full Waveform Inversion in resolving fracture damage zones around a modelled geological disposal facility in granite

    NASA Astrophysics Data System (ADS)

    Bentham, H. L. M.; Morgan, J. V.; Angus, D. A.

    2016-12-01

    The UK has a large volume of high level and intermediate level radioactive waste and government policy is to dispose of this waste in a Geological Disposal Facility (GDF). This will be a highly-engineered facility capable of isolating radioactive waste within multiple protective barriers, deep underground, to ensure that no harmful quantities of radioactivity ever reach the surface environment. Although no specific GDF site in the UK has been chosen, granite is one of the candidate host rocks due to its strength, in engineering terms, and because of its low permeability in consideration of groundwater movement. We design time-lapse seismic surveys to characterise geological models of naturally fractured granite with GDF-related tunnel damage zones at a potential disposal depth of 1000 m (the UK GDF might be shallower). Additionally, we use effective medium models to calculate the velocity change when the fracture density is increased in the damage zones, and find a reduction of 60 m/s in P-wave velocity when the fracture density is doubled. Next, we simulate seismic surveys and apply 3D Full Waveform Inversion (FWI) to see how well we can recover the low-velocity damage zones. Furthermore we evaluate the effectiveness of using a survey design consisting of surface and tunnel receivers (a combined array) to resolve the target. After applying FWI we find the velocity anomaly within the damage zone can be resolved to within 2 m/s (3%) and the shape of the damage zone is resolved to 12.5 m (within a single grid cell). Using the combined array we are able to resolve the anomaly strength and shape more completely. When we add further complexity to the model by including tunnel infrastructure, we conclude the combined array is essential in recovering the tunnel damage zone. Our findings show that it is beneficial to use 3D FWI and novel survey designs for characterising subtle variations as may be present in granite, information that could assist in the GDF site selection

  2. Facile and scalable disposable sensor based on laser engraved graphene for electrochemical detection of glucose

    NASA Astrophysics Data System (ADS)

    Tehrani, Farshad; Bavarian, Behzad

    2016-06-01

    A novel and highly sensitive disposable glucose sensor strip was developed using direct laser engraved graphene (DLEG) decorated with pulse deposited copper nanocubes (CuNCs). The high reproducibility (96.8%), stability (97.4%) and low cost demonstrated by this 3-step fabrication method indicates that it could be used for high volume manufacturing of disposable glucose strips. The fabrication method also allows for a high degree of flexibility, allowing for control of the electrode size, design, and functionalization method. Additionally, the excellent selectivity and sensitivity (4,532.2 μA/mM.cm2), low detection limit (250 nM), and suitable linear range of 25 μM–4 mM, suggests that these sensors may be a great potential platform for glucose detection within the physiological range for tear, saliva, and/or sweat.

  3. Facile and scalable disposable sensor based on laser engraved graphene for electrochemical detection of glucose.

    PubMed

    Tehrani, Farshad; Bavarian, Behzad

    2016-06-16

    A novel and highly sensitive disposable glucose sensor strip was developed using direct laser engraved graphene (DLEG) decorated with pulse deposited copper nanocubes (CuNCs). The high reproducibility (96.8%), stability (97.4%) and low cost demonstrated by this 3-step fabrication method indicates that it could be used for high volume manufacturing of disposable glucose strips. The fabrication method also allows for a high degree of flexibility, allowing for control of the electrode size, design, and functionalization method. Additionally, the excellent selectivity and sensitivity (4,532.2 μA/mM.cm(2)), low detection limit (250 nM), and suitable linear range of 25 μM-4 mM, suggests that these sensors may be a great potential platform for glucose detection within the physiological range for tear, saliva, and/or sweat.

  4. Facile and scalable disposable sensor based on laser engraved graphene for electrochemical detection of glucose

    PubMed Central

    Tehrani, Farshad; Bavarian, Behzad

    2016-01-01

    A novel and highly sensitive disposable glucose sensor strip was developed using direct laser engraved graphene (DLEG) decorated with pulse deposited copper nanocubes (CuNCs). The high reproducibility (96.8%), stability (97.4%) and low cost demonstrated by this 3-step fabrication method indicates that it could be used for high volume manufacturing of disposable glucose strips. The fabrication method also allows for a high degree of flexibility, allowing for control of the electrode size, design, and functionalization method. Additionally, the excellent selectivity and sensitivity (4,532.2 μA/mM.cm2), low detection limit (250 nM), and suitable linear range of 25 μM–4 mM, suggests that these sensors may be a great potential platform for glucose detection within the physiological range for tear, saliva, and/or sweat. PMID:27306706

  5. DISTRIBUTION COEFICIENTS (KD) GENERATED FROM A CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY

    SciTech Connect

    Almond, P.; Kaplan, D.

    2011-04-25

    Core samples originating from Vault 4, Cell E of the Saltstone Disposal Facility (SDF) were collected in September of 2008 (Hansen and Crawford 2009, Smith 2008) and sent to SRNL to measure chemical and physical properties of the material including visual uniformity, mineralogy, microstructure, density, porosity, distribution coefficients (K{sub d}), and chemical composition. Some data from these experiments have been reported (Cozzi and Duncan 2010). In this study, leaching experiments were conducted with a single core sample under conditions that are representative of saltstone performance. In separate experiments, reducing and oxidizing environments were targeted to obtain solubility and Kd values from the measurable species identified in the solid and aqueous leachate. This study was designed to provide insight into how readily species immobilized in saltstone will leach from the saltstone under oxidizing conditions simulating the edge of a saltstone monolith and under reducing conditions, targeting conditions within the saltstone monolith. Core samples were taken from saltstone poured in December of 2007 giving a cure time of nine months in the cell and a total of thirty months before leaching experiments began in June 2010. The saltstone from Vault 4, Cell E is comprised of blast furnace slag, class F fly ash, portland cement, and Deliquification, Dissolution, and Adjustment (DDA) Batch 2 salt solution. The salt solution was previously analyzed from a sample of Tank 50 salt solution and characterized in the 4QCY07 Waste Acceptance Criteria (WAC) report (Zeigler and Bibler 2009). Subsequent to Tank 50 analysis, additional solution was added to the tank solution from the Effluent Treatment Project as well as from inleakage from Tank 50 pump bearings (Cozzi and Duncan 2010). Core samples were taken from three locations and at three depths at each location using a two-inch diameter concrete coring bit (1-1, 1-2, 1-3; 2-1, 2-2, 2-3; 3-1, 3-2, 3-3) (Hansen and

  6. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design.

    SciTech Connect

    Cochran, John R.; Hardin, Ernest

    2015-07-01

    This report presents conceptual design information for a system to handle and emplace packages containing radioactive waste, in boreholes 16,400 ft deep or possibly deeper. Its intended use is for a design selection study that compares the costs and risks associated with two emplacement methods: drill-string and wireline emplacement. The deep borehole disposal (DBD) concept calls for siting a borehole (or array of boreholes) that penetrate crystalline basement rock to a depth below surface of about 16,400 ft (5 km). Waste packages would be emplaced in the lower 6,560 ft (2 km) of the borehole, with sealing of appropriate portions of the upper 9,840 ft (3 km). A deep borehole field test (DBFT) is planned to test and refine the DBD concept. The DBFT is a scientific and engineering experiment, conducted at full-scale, in-situ, without radioactive waste. Waste handling operations are conceptualized to begin with the onsite receipt of a purpose-built Type B shipping cask, that contains a waste package. Emplacement operations begin when the cask is upended over the borehole, locked to a receiving flange or collar. The scope of emplacement includes activities to lower waste packages to total depth, and to retrieve them back to the surface when necessary for any reason. This report describes three concepts for the handling and emplacement of the waste packages: 1) a concept proposed by Woodward-Clyde Consultants in 1983; 2) an updated version of the 1983 concept developed for the DBFT; and 3) a new concept in which individual waste packages would be lowered to depth using a wireline. The systems described here could be adapted to different waste forms, but for design of waste packaging, handling, and emplacement systems the reference waste forms are DOE-owned high- level waste including Cs/Sr capsules and bulk granular HLW from fuel processing. Handling and Emplacement Options for Deep Borehole Disposal Conceptual Design July 23, 2015 iv ACKNOWLEDGEMENTS This report has

  7. Functional design criteria for Project W-252, Phase II Liquid Effluent Treatment and Disposal: Revision 1

    SciTech Connect

    Hatch, C.E.

    1994-11-10

    This document provides the functional design criteria required for the Phase 2 Liquid Effluent Treatment and Disposal Project, Project W-252. Project W-252 shall provide new facilities and existing facility modifications required to implement Best Available Technology/All Known, Available, and Reasonable Methods of Prevention, Control, and Treatment (BAT/AKART) for the 200 East Phase II Liquid Effluent Streams. The project will also provide a 200 East Area Phase II Effluent Collection System (PTECS) for connection to a disposal system for relevant effluent streams to which BAT/AKART has been applied. Liquid wastestreams generated in the 200 East Area are currently discharged to the soil column. Included in these wastestreams are cooling water, steam condensate, raw water, and sanitary wastewaters. It is the policy of the DOE that the use of soil columns to treat and retain radionuclides and nonradioactive contaminants be discontinued at the earliest practical time in favor of wastewater treatment and waste minimization. In 1989, the DOE entered into an interagency agreement with Ecology and EPA. This agreement is referred to as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Project W-252 is one of the projects required to achieve the milestones set forth in the Tri-Party Agreement. One of the milestones requires BAT/AKART implementation for Phase II streams by October 1997. This Functional Design Criteria (FDC) document provides the technical baseline required to initiate Project W-252 to meet the Tri-Party Agreement milestone for the application of BAT/AKART to the Phase II effluents.

  8. Nasreya: a treatment and disposal facility for industrial hazardous waste in Alexandria, Egypt: phase I.

    PubMed

    Ramadan, Adham R; Kock, Per; Nadim, Amani

    2005-04-01

    A facility for the treatment and disposal of industrial hazardous waste has been established in Alexandria, Egypt. Phase I of the facility encompassing a secure landfill and solar evaporation ponds is ready to receive waste, and Phase II encompassing physico-chemical treatment, solidification, and interim storage is underway. The facility, the Nasreya Centre, is the first of its kind in Egypt, and represents the nucleus for the integration, improvement and further expansion of different hazardous waste management practices and services in Alexandria. It has been developed within the overall legal framework of the Egyptian Law for the Environment, and is expected to improve prospects for enforcement of the regulatory requirements specified in this law. It has been developed with the overall aim of promoting the establishment of an integrated industrial hazardous waste management system in Alexandria, serving as a demonstration to be replicated elsewhere in Egypt. For Phase I, the Centre only accepts inorganic industrial wastes. In this respect, a waste acceptance policy has been developed, which is expected to be reviewed during Phase II, with an expansion of the waste types accepted.

  9. Centrifuge modeling of radioactive waste migration through backfill in a near surface disposal facility

    SciTech Connect

    Gurumoorthy, C.; Kusakabe, O.

    2007-07-01

    Investigations on the performance of backfill barrier in Near Surface Disposal Facility (NSDF) for radioactive wastes are important to ensure the long term safety of such disposal option. Favorable condition to delay migration of radionuclides from disposed waste to far fields is diffusion process. However, advective dispersion/diffusion mechanism plays an important role due to changes in backfill over a period of time. In order to understand these mechanisms, detailed laboratory experiments are usually conducted for developing mathematical models to assess the behaviour of backfill. However, these experiments are time consuming and suffer with the limitations due to material complexity. Also, there are constraints associated with validation of theoretical predictions due to intricacy of boundary conditions as well as the time scale is quite different as compared to the time required for completion of the processes in the field. Keeping in view these aspects, centrifuge modeling technique has been adopted by various researchers to model and understand various geo-environment problems in order to provide a link between the real life situation termed as the 'Prototype' and its model, which is exposed to a higher gravitational field. An attempt has been made in this paper to investigate the feasibility of this technique to model advective dispersion/diffusion mechanism of radionuclides through saturated Bentonite-Sand (B:S) backfill. Various stages of centrifuge modeling are highlighted. Column tests were conducted in the centrifuge to evaluate the hydraulic conductivity of B:S mixture under prototype NSDF stress conditions. Results showed that steady state hydraulic conductivity under saturated conditions was 2.86 10{sup -11} m/sec. Studies indicate the feasibility of centrifuge modeling technique and usefulness to model advective diffusion of radionuclides through B:S backfill. (authors)

  10. (237)Np analytical method using (239)Np tracers and application to a contaminated nuclear disposal facility.

    PubMed

    Snow, Mathew S; Morrison, Samuel S; Clark, Sue B; Olson, John E; Watrous, Matthew G

    2017-06-01

    Environmental (237)Np analyses are challenged by low (237)Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive (237)Np analytical approach employing the short lived (239)Np (t1/2 = 2.3 days) as a chemical yield tracer followed by (237)Np quantification using inductively coupled plasma-mass spectrometry. (239)Np tracer is obtained via separation from a (243)Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 10(6) and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level (237)Np contamination within 600 m of this site, with maximum (237)Np concentrations on the order of 10(3) times greater than nuclear weapons testing fallout levels. Copyright © 2017 Elsevier Ltd. All rights reserved.

  11. 237Np analytical method using 239Np tracers and application to a contaminated nuclear disposal facility

    DOE PAGES

    Snow, Mathew S.; Morrison, Samuel S.; Clark, Sue B.; ...

    2017-03-21

    In this study, environmental 237Np analyses are challenged by low 237Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237Np analytical approach employing the short lived 239Np (t1/2 = 2.3 days) as a chemical yield tracer followed by 237Np quantification using inductively coupled plasma-mass spectrometry. 239Np tracer is obtained via separation from a 243Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on themore » order of 106 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237Np contamination within 600 m of this site, with maximum 237Np concentrations on the order of 103 times greater than nuclear weapons testing fallout levels.« less

  12. Large laser system facility design

    SciTech Connect

    Gilmartin, T.J.

    1983-08-09

    Optical stability of foundations and support structures, environmental control, close-in subsystem integration, spatial organization, materiel flow and access to remote subsystems is discussed and compared for four laser facilities: The Special Isotope Separation Laboratory, Argus, Shiva/Nova, and Firepond.

  13. Comparative approaches to siting low-level radioactive waste disposal facilities

    SciTech Connect

    Newberry, W.F.

    1994-07-01

    This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

  14. Performance assessment handbook for low-level radioactive waste disposal facilities

    SciTech Connect

    Seitz, R.R.; Garcia, R.S.; Kostelnik, K.M.; Starmer, R.J.

    1992-02-01

    Performance assessments of proposed low-level radioactive waste disposal facilities must be conducted to support licensing. This handbook provides a reference document that can be used as a resource by management and staff responsible for performance assessments. Brief discussions describe the performance assessment process and emphasize selected critical aspects of the process. References are also provided for additional information on many aspects of the performance assessment process. The user's manual for the National Low-Level Waste Management Program's Performance Assessment Center (PAC) on the Idaho National Engineering Laboratory Cray computer is included as Appendix A. The PAC provides users an opportunity to experiment with a number of performance assessment computer codes on a Cray computer. Appendix B describes input data required for 22 performance assessment codes.

  15. Effluent variability study for the 200 area treated effluent disposal facility

    SciTech Connect

    Chou, C.J., Westinghouse Hanford

    1996-07-12

    The variability of permitted constituents in grab samples and 24-hr composites of liquid effluent discharged to the Treated Effluent Disposal Facility (TEDF) in the 200 East Area of the Hanford Site was evaluated for the period July 1995 through April 1996. The variability study was required as a condition of the wastewater discharge permit issued by the State of Washington Department of Ecology. Results of the statistical evaluation indicated that (1) except for iron, and possibly chloride, there is a very low probability of exceeding existing permit limits, (2) seasonal effects related to intake water quality account for the variability in several chemical constituents and (3) sample type (grab vs 24-hr composite) have little if any effect on monthly mean constituent concentrations.

  16. Transport of spent fuel from reactors to DOE storage/disposal facilities - a parametric study

    SciTech Connect

    Johnson, E.R.; Saverot, P.M.

    1997-09-01

    The amount of spent fuel from US commercial nuclear power plants that will be shipped to US DOE disposal facilities is expected to peak out at about 3000 MTU. A number of concerns including safety, emergency response, and traffic impacts, have been expressed regarding the large number of shipments that will be required to move this spent fuel. This article develops parametrically the numbers of shipments required to move 3000 MTU/year in the form of spent fuel under a variety of cask capacities and assumptions of fuel characteristics as well as the number of casks needed. In addition incremental traffic impact on roads and rail lines under a variety of conditions is also analyzed. 3 refs., 3 tabs.

  17. HEU to LEU conversion and blending facility: Metal blending alternative to produce LEU oxide for disposal

    SciTech Connect

    1995-09-01

    US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form more proliferation- resistant than the original form. Blending HEU (highly enriched uranium) with less-enriched uranium to form LEU has been proposed as a disposition option. Five technologies are being assessed for blending HEU. This document provides data to be used in environmental impact analysis for the HEU-LEU disposition option that uses metal blending with an oxide waste product. It is divided into: mission and assumptions, conversion and blending facility descriptions, process descriptions and requirements, resource needs, employment needs, waste and emissions from plant, hazards discussion, and intersite transportation.

  18. National Ignition Facility Title II Design Plan

    SciTech Connect

    Kumpan, S

    1997-03-01

    This National Ignition Facility (NIF) Title II Design Plan defines the work to be performed by the NIF Project Team between November 1996, when the U.S. Department of Energy (DOE) reviewed Title I design and authorized the initiation of Title H design and specific long-lead procurements, and September 1998, when Title 11 design will be completed.

  19. Obstacle factors and overcoming plans of public communication: With an emphasis on radioactive waste disposal facility siting

    SciTech Connect

    Yoo, Hae-Woon; Oh, Chang-Taeg

    1996-12-31

    Korea is confronting a serious social conflict, which is phenomenon of local residents reaction to radioactive waste disposal facility. This phenomenon is traced back to the reason that the project sponsors and local residents do not communicate sufficiently each other. Accordingly, in order to overcome local residents` reaction to radioactive waste disposal facility siting effectively, it is absolutely necessary to consider the way of solutions and strategies with regard to obstacle factors for public communication. In this content, this study will review three cases (An-myon Island, Gul-up Island, Yang-yang) on local residents reaction to facility siting. As a result of analysis, authoritarian behavior of project sponsors, local stigma, risk, antinuclear activities of environmental group, failures in siting the radioactive waste disposal facility, etc. has negative impact on public communication of the radioactive waste disposal facility siting. In this study, 5 strategies (reform of project sponsor`s authoritarianism, incentive offer, strengthening PA activities, more active talks with environmental groups, promoting credibility of project sponsors) arc suggested to cope with obstacle factors of public communication.

  20. Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0

    SciTech Connect

    Wijesinghe, A.M.; Shaffer, R.J.

    1996-01-15

    The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

  1. Tritium Plume Dynamics in the Shallow Unsaturated Zone Adjacent to an Arid Waste Disposal Facility

    NASA Astrophysics Data System (ADS)

    Maples, S.; Andraski, B. J.; Stonestrom, D. A.; Cooper, C. A.; Michel, R. L.; Pohll, G. M.

    2012-12-01

    Previous studies at the U.S. Geological Survey's Amargosa Desert Research Site (ADRS) in southern Nevada have documented two plumes of tritiated water-vapor (3HHOg) adjacent to a closed, commercial low-level radioactive waste disposal facility. Wastes were disposed on-site from 1962-92. Tritium has moved long distances (> 400 m) through a shallow (1-2-m depth) dry gravelly layer—orders of magnitude further than anticipated by standard transport models. Geostatistical methods, spatial moment analyses and tritium flux calculations were applied to assess shallow plume dynamics. A grid-based plant-water sampling method was utilized to infer detailed, field-scale 3HHOg concentrations at 5-yr intervals during 2001-11. Results indicate that gravel-layer 3HHOg mass diminished faster than would be expected from radioactive decay (~70% in 10 yr). Both plumes exhibited center-of-mass stability, suggesting that bulk-plume movement is minimal during the period of study. Nonetheless, evidence of localized lateral advancement along some margins, combined with increases in the spatial covariance of concentration distribution, indicates intra-plume mass redistribution is ongoing. Previous studies have recognized that vertical movement of tritiated water from sub-root-zone gravel into the root-zone contributes to atmospheric release via evapotranspiration. Estimates of lateral and vertical tritium fluxes during the study period indicate (1) vertical tritiated water fluxes were dominated by diffusive-vapor fluxes (> 90%), and (2) vertical diffusive-vapor fluxes were roughly an order of magnitude greater than lateral diffusive-vapor fluxes. This behavior highlights the importance of the atmosphere as a tritium sink. Estimates of cumulative vertical diffusive-vapor flux and radioactive decay with time were comparable to observed declines in total shallow plume mass with time. This suggests observed changes in plume mass may (1) be attributed, in considerable part, to these removal

  2. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    SciTech Connect

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  3. Design considerations for healthcare simulation facilities.

    PubMed

    Seropian, Michael; Lavey, Robert

    2010-12-01

    The number of simulation facilities across the United States and internationally is growing rapidly. The capital investment required can be substantive regardless of size. This article focuses on ways to optimize expenditures and maximize utility. Several key factors will play decisive roles in the successful launch of a new simulation facility. Mission/vision, budget, functional need, and space are partners in determining the final design of the simulation facility. Ideally, the budget is based on the functional requirements and desired capacity; but when this is not the case, of course, the owner must prioritize the needs of the new center. The type of space allocated for the facility is also critical and can seriously impact the budget because renovating a space that is fitted for another purpose versus constructing the center in an open shell space can add considerable cost. A well-balanced design team led by a diligent and knowledgeable project manager who can keep the team focused is integral to the success of designing and constructing a new facility. Users should inform themselves about each of the issues that a design team may consider to ensure that the issues are resolved in a way that meets the needs and vision of the program(s). A simulation facility, such as any education facility, should be built around the concepts of the overall mission, vision, and values of the institution(s) and stakeholder(s). For any new educational facility to be a success, the thoughts, ideas, and creativity of the owner, users, and stakeholders must find its way into the ultimate built environment. The experience base of simulation facility design is fragmented and not standardized. Therefore, we live at a time where the risk of ineffective design is higher than one would like given the costs involved. It behooves the owner to set parameters with the planning and design team that they want a balanced, controlled, collaborative, and inclusive design process.

  4. 78 FR 29687 - Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-21

    ... AGENCY 40 CFR Part 228 Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation...) Atchafalaya-West Ocean Disposal Site (ODMDS-West) as a permanent MPRSA Section 102(c) ocean dredged material... Management and Monitoring Plan E. Ocean Dumping Site Designation Criteria --General Selection Criteria...

  5. Design Standards for School Art Facilities

    ERIC Educational Resources Information Center

    National Art Education Association, 2015

    2015-01-01

    "Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

  6. Design Standards for School Art Facilities

    ERIC Educational Resources Information Center

    National Art Education Association, 2015

    2015-01-01

    "Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

  7. STAO Science Laboratory Facilities Design Guide.

    ERIC Educational Resources Information Center

    Mackellar, Ian, Ed.

    This design guide offers guidance to science educators, architects, and others concerned with the provision of science accommodations in Ontario, Canada, either through new construction or the adaptation of existing buildings. The publication is not a blueprint for facilities nor an attempt to standardize all science programs and facilities; it is…

  8. Design considerations of the national transonic facility

    NASA Technical Reports Server (NTRS)

    Baals, D. D.

    1976-01-01

    The inability of existing wind tunnels to provide aerodynamic test data at transonic speeds and flight Reynolds numbers was examined. The proposed transonic facility is a high Reynolds number transonic wind tunnel designed to meet the research and development needs of industry, and the scientific community. The facility employs the cryogenic approach to achieve high transonic Reynolds numbers at acceptable model loads and tunnel power. By using temperature as a test variable, a unique capability to separate scale effects from model aeroelastic effects is provided. The performance envelope of the facility is shown to provide a ten fold increase in transonic Reynolds number capability compared to currently available facilities.

  9. (US low-level radioactive waste management facility design, construction, and operation): Foreign trip report, July 22--30, 1989

    SciTech Connect

    Van Hoesen, S.D.; Bolinsky, J.

    1989-08-02

    The Martin Marietta Energy Systems, Inc., Team, consisting of representatives of the Engineering Division and Oak Ridge National Laboratory (ORNL), participated in a technology exchange program on French and US low-level radioactive waste (LLW) management facility design, construction, and operation. Meetings were held at the Agence National pour la Gestion des Dechets Radioactif (ANDRA) offices in Paris to review the designs for the new French LLW disposal facility, the Cente de Stockage de l'Aube (CSA), and the new ORNL LLW disposal project, the Interim Waste Management Facility (IWMF), and the results of the French LLW disposal facility cover experiment at St. Sauveur. Visits were made to the operating LLW disposal facility, the Centre de Stockage de la Manche (CSM), the LLW conditioning facilities at the La Hague Reprocessing Facility, and the St. Saueveur Disposal Cap Experiment to discuss design, construction, and operating experience. A visit was also made to the CSA site to view the progress made in construction of the new facility.

  10. Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site

    SciTech Connect

    L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

    2008-03-01

    The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative

  11. Evaluation of groundwater monitoring results at the Hanford Site 200 Area Treated Effluent Disposal Facility

    SciTech Connect

    Barnett, D.B.

    1998-09-01

    The Hanford Site 200 Area Treated Effluent Disposal Facility (TEDF) has operated since June 1995. Groundwater monitoring has been conducted quarterly in the three wells surrounding the facility since 1992, with contributing data from nearby B Pond System wells. Cumulative hydrologic and geochemical information from the TEDF well network and other surrounding wells indicate no discernable effects of TEDF operations on the uppermost aquifer in the vicinity of the TEDF. The lateral consistency and impermeable nature of the Ringold Formation lower mud unit, and the contrasts in hydraulic conductivity between this unit and the vadose zone sediments of the Hanford formation suggest that TEDF effluent is spreading laterally with negligible mounding or downward movement into the uppermost aquifer. Hydrographs of TEDF wells show that TEDF operations have had no detectable effects on hydraulic heads in the uppermost aquifer, but show a continuing decay of the hydraulic mound generated by past operations at the B Pond System. Comparison of groundwater geochemistry from TEDF wells and other, nearby RCRA wells suggests that groundwater beneath TEDF is unique; different from both effluent entering TEDF and groundwater in the B Pond area. Tritium concentrations, major ionic proportions, and lower-than-background concentrations of other species suggest that groundwater in the uppermost aquifer beneath the TEDF bears characteristics of water in the upper basalt confined aquifer system. This report recommends retaining the current groundwater well network at the TEDF, but with a reduction of sampling/analysis frequency and some modifications to the list of constituents sought.

  12. Performance-assessment progress for the Rozan low-level waste disposal facility

    SciTech Connect

    Smietanski, L.; Mitrega, J.; Frankowski, Z.

    1995-12-31

    The paper presents a condensed progress report on the performance assessment of Poland`s low-level waste disposal facility which is operating since 1961. The Rozan repository is of near-surface type with facilities which are the concrete fortifications built about 1910. Site characterization activities supplied information on regional geology, geohydrology, climatic and hydrologic conditions and terrain surface evolution due to geodynamic processes. Field surveys enabled to decode lithological, hydrogeological and geochemical site specific conditions. From the laboratory tests the data on groundwater chemistry and soil geochemical and hydraulic characteristics were obtained. The site geohydrologic main vulnerable element is the upmost directly endangered unconfined aquifer which is perched in relation to the region-wide hydraulic system. Heterogeneity of this system reflects in a wide range of hydraulic conductivity and thickness variations. It strongly affects velocity and flow directions. The chemistry of groundwater is unstable due to large sensitivity to external impacts. Modeling of the migration of the critical long-lived radionuclides Tc-99, U-238 and Pu-239 showed that the nearly 20 m thick unsaturated zone plays crucial role as an effective protective barrier. These radionuclides constitute minor part of the total inventory. Modeling of the development of the H-3 plume pointed out the role the macrodispersion plays in the unsaturated zone beneath the repository.

  13. Use of engineered soils beneath low-level radioactive waste disposal facilities

    SciTech Connect

    Sandford, T.C.; Humphrey, D.N.; DeMascio, F.A.

    1993-03-01

    Current regulations are oriented toward locating low-level radioactive waste disposal facilities on sites that have a substantial natural soil barrier and are above the groundwater table. In some of the northern states, like Maine, the overburden soils are glacially derived and in most places provide a thin cover over bedrock with a high groundwater table. Thus, the orientation of current regulations can severely limit the availability of suitable sites. A common characteristic of many locations in glaciated regions is the rapid change of soil types that may occur and the heterogeneity within a given soil type. In addition, the bedrock may be fractured, providing avenues for water movement. A reliable characterization of these sites can be difficult, even with a detailed subsurface exploration program. Moreover, fluctuating groundwater and frost as well as the natural deposition processes have introduced macro features such as cracks, fissures, sand and silt seams, and root holes. The significant effect that these macro features have on the permeability and adsorptive capacity of a large mass is often ignored or poorly accounted for in the analyses. This paper will examine an alternate approach, which is to use engineered soils as a substitute for some or all of the natural soil and to treat the fractures in the underlying bedrock. The site selection would no longer be primarily determined by the natural soil and rock and could even be placed in locations with no existing soils. Engineered soils can be used for below- or aboveground facilities.

  14. Topside facilities design for Hutton TLP

    SciTech Connect

    Wingate, P.M.; Hasz, J.W.; McGee, M.D.

    1983-09-01

    The Hutton North Sea field is to be developed using the world's first commercial Tension Leg Platform (TLP). This paper explains how the choice of a TLP, with its dynamic behaviour and structural configuration, affected the design of the topside facilities. The problems faced by facilities engineers are described as are the methods used to resolve them. The nature of the problems described are general to TLPs, consequently the material presented is applicable to designs of the future.

  15. Wastewater Disposal from Unconventional Oil and Gas Development Degrades Stream Quality at a West Virginia Injection Facility.

    PubMed

    Akob, Denise M; Mumford, Adam C; Orem, William; Engle, Mark A; Klinges, J Grace; Kent, Douglas B; Cozzarelli, Isabelle M

    2016-06-07

    The development of unconventional oil and gas (UOG) resources has rapidly increased in recent years; however, the environmental impacts and risks are poorly understood. A single well can generate millions of liters of wastewater, representing a mixture of formation brine and injected hydraulic fracturing fluids. One of the most common methods for wastewater disposal is underground injection; we are assessing potential risks of this method through an intensive, interdisciplinary study at an injection disposal facility in West Virginia. In June 2014, waters collected downstream from the site had elevated specific conductance (416 μS/cm) and Na, Cl, Ba, Br, Sr, and Li concentrations, compared to upstream, background waters (conductivity, 74 μS/cm). Elevated TDS, a marker of UOG wastewater, provided an early indication of impacts in the stream. Wastewater inputs are also evident by changes in (87)Sr/(86)Sr in streamwater adjacent to the disposal facility. Sediments downstream from the facility were enriched in Ra and had high bioavailable Fe(III) concentrations relative to upstream sediments. Microbial communities in downstream sediments had lower diversity and shifts in composition. Although the hydrologic pathways were not able to be assessed, these data provide evidence demonstrating that activities at the disposal facility are impacting a nearby stream and altering the biogeochemistry of nearby ecosystems.

  16. Wastewater disposal from unconventional oil and gas development degrades stream quality at a West Virginia injection facility

    USGS Publications Warehouse

    Akob, Denise M.; Mumford, Adam; Orem, William H.; Engle, Mark A.; Klinges, Julia (Grace); Kent, Douglas B.; Cozzarelli, Isabelle M.

    2016-01-01

    The development of unconventional oil and gas (UOG) resources has rapidly increased in recent years; however, the environmental impacts and risks are poorly understood. A single well can generate millions of liters of wastewater, representing a mixture of formation brine and injected hydraulic fracturing fluids. One of the most common methods for wastewater disposal is underground injection; we are assessing potential risks of this method through an intensive, interdisciplinary study at an injection disposal facility in West Virginia. In June 2014, waters collected downstream from the site had elevated specific conductance (416 μS/cm) and Na, Cl, Ba, Br, Sr, and Li concentrations, compared to upstream, background waters (conductivity, 74 μS/cm). Elevated TDS, a marker of UOG wastewater, provided an early indication of impacts in the stream. Wastewater inputs are also evident by changes in 87Sr/86Sr in streamwater adjacent to the disposal facility. Sediments downstream from the facility were enriched in Ra and had high bioavailable Fe(III) concentrations relative to upstream sediments. Microbial communities in downstream sediments had lower diversity and shifts in composition. Although the hydrologic pathways were not able to be assessed, these data provide evidence demonstrating that activities at the disposal facility are impacting a nearby stream and altering the biogeochemistry of nearby ecosystems.

  17. Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407

    SciTech Connect

    Walker, Stuart

    2013-07-01

    This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

  18. Mixed and low-level radioactive waste disposal from the Argonne National Laboratory-East Map Tube Facility

    SciTech Connect

    Wescott, J.B.; Moos, L.P.

    1995-07-01

    The Map Tube Facility was a storage unit for small, highly radioactive objects. The facility consisted of 129 cast-iron pipes cast vertically in a concrete monolithic structure. The objects were packaged and placed into the pipes for storage prior to disposal or reuse in research experiments. Deterioration of the facility allowed water to enter the pipes. Release of this contaminated water has resulted in radiological contamination of underlying soil and groundwater. Sediment, principally corrosion products, collected in the bottom of the pipes. Decontamination and decommissioning of the Map Tube Facility generated a large quantity of radioactive mixed and low-level waste. All low-level and mixed waste that can not be treated on-site is sent to the Westinghouse Hanford Company (WHC) in Richland, Washington for storage or disposal. Because of the difficulty and cost of disposing radioactive mixed waste, a great amount of effort was expended to limit the mixed waste volume. The final volume of mixed waste was approximately 99 percent less than originally generated with total waste disposal costs being reduced by roughly two-thirds.

  19. REPORT ON THE HOMELAND SECURITY WORKSHOP ON TRANSPORT AND DISPOSAL OF WASTES FROM FACILITIES CONTAMINATED WITH CHEMICAL AND BIOLOGICAL AGENTS

    EPA Science Inventory

    This report summarizes discussions from the "Homeland Security Workshop on Transport and Disposal of Wastes From Facilities Contaminated With Chemical or Biological Agents." The workshop was held on May 28-30, 2003, in Cincinnati, Ohio, and its objectives were to:

    .Documen...

  20. 26 CFR 17.1 - Industrial development bonds used to provide solid waste disposal facilities; temporary rules.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 26 Internal Revenue 14 2010-04-01 2010-04-01 false Industrial development bonds used to provide solid waste disposal facilities; temporary rules. 17.1 Section 17.1 Internal Revenue INTERNAL REVENUE... UNDER 26 U.S.C. 103(c) § 17.1 Industrial development bonds used to provide solid waste...

  1. 26 CFR 17.1 - Industrial development bonds used to provide solid waste disposal facilities; temporary rules.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 14 2011-04-01 2010-04-01 true Industrial development bonds used to provide solid waste disposal facilities; temporary rules. 17.1 Section 17.1 Internal Revenue INTERNAL REVENUE... UNDER 26 U.S.C. 103(c) § 17.1 Industrial development bonds used to provide solid waste...

  2. Impacts on non-human biota from a generic geological disposal facility for radioactive waste: some key assessment issues.

    PubMed

    Robinson, C A; Smith, K L; Norris, S

    2010-06-01

    This paper provides an overview of key issues associated with the application of currently available biota dose assessment methods to consideration of potential environmental impacts from geological disposal facilities. It explores philosophical, methodological and practical assessment issues and reviews the implications of test assessment results in the context of recent and on-going challenges and debates.

  3. Design Guidance for Confined Disposal Facility Lateral Seepage Control

    DTIC Science & Technology

    2005-09-01

    polyethylene (HDPE) liner. The trencher operates by cutting through soil using a chain-saw type apparatus attached to the boom of a crawler-mounted vehicle...effluent during filling operations (USEPA 1994), (2) surface runoff during precipitation after closure (USEPA 1994), (3) seepage through perimeter...Washington Headquarters Services, Directorate for Information Operations and Reports, 1215 Jefferson Davis Highway, Suite 1204, Arlington VA 22202

  4. Linking RESRAD-OFFSITE and HYDROGEOCHEM Model for Performance Assessment of Low-Level Radioactive Waste Disposal Facility - 13429

    SciTech Connect

    Lin, Wen-Sheng; Yu, Charley; Cheng, Jing-Jy; Kamboj, Sunita; Gnanapragasam, Emmanuel; Liu, Chen-Wuing; Li, Ming-Hsu

    2013-07-01

    Performance assessments are crucial steps for the long-term radiological safety requirements of low-level waste (LLW) disposal facility. How much concentration of radionuclides released from the near-field to biosphere and what radiation exposure levels of an individual can influence on the satisfactory performance of the LLW disposal facility and safety disposal environment. Performance assessment methodology for the radioactive waste disposal consists of the reactive transport modeling of safety-concerned radionuclides released from the near-field to the far-field, and the potential exposure pathways and the movements of radionuclides through the geosphere, biosphere and man of which the accompanying dose. Therefore, the integration of hydrogeochemical transport model and dose assessment code, HYDROGEOCHEM code and RESRAD family of codes is imperative. The RESRAD family of codes such as RESRAD-OFFSITE computer code can evaluate the radiological dose and excess cancer risk to an individual who is exposed while located within or outside the area of initial (primary) contamination. The HYDROGEOCHEM is a 3-D numerical model of fluid flow, thermal, hydrologic transport, and biogeochemical kinetic and equilibrium reactions in saturated and unsaturated media. The HYDROGEOCHEM model can also simulate the crucial geochemical mechanism, such as the effect of redox processes on the adsorption/desorption, hydrogeochemical influences on concrete degradation, adsorption/desorption of radionuclides (i.e., surface complexation model) between solid and liquid phase in geochemically dynamic environments. To investigate the safety assessment of LLW disposal facility, linking RESRAD-OFFSITE and HYDROGEOCHEM model can provide detailed tools of confidence in the protectiveness of the human health and environmental impact for safety assessment of LLW disposal facility. (authors)

  5. High efficiency waste to energy facility -- Pilot plant design

    SciTech Connect

    Orita, Norihiko; Kawahara, Yuuzou; Takahashi, Kazuyoshi; Yamauchi, Toru; Hosoda, Takuo

    1998-07-01

    Waste To Energy facilities are commonly acceptable to the environment and give benefits in two main areas: one is a hygienic waste disposal and another is waste heat energy recovery to save fossil fuel consumption. Recovered energy is used for electricity supply, and it is required to increase the efficiency of refuse to electric energy conversion, and to spread the plant construction throughout the country of Japan, by the government. The national project started in 1992, and pilot plant design details were established in 1995. The objective of the project is to get 30% of energy conversion efficiency through the measure by raising the steam temperature and pressure to 500 C and 9.8 MPa respectively. The pilot plant is operating under the design conditions, which verify the success of applied technologies. This paper describes key technologies which were used to design the refuse burning boiler, which generates the highest steam temperature and pressure steam.

  6. Performance Confirmation Strategies for the Waste Isolation Pilot Plant - A Historical Perspective from an Operating Disposal Facility - 12248

    SciTech Connect

    Wagner, Steve

    2012-07-01

    Performance confirmation is an important element of the Waste Isolation Pilot Plant (WIPP) program. Performance confirmation was first used during the early WIPP site characterization phase to focus experimental activities that address the development of probabilistic repository performance models and to address stakeholder assurance needs. The program is currently used to analyze the conditions of the repository and its surroundings to ensure that the basis for the repository's long-term radioactive waste containment predictions is valid. This basis is related to the parameters, assumptions, conceptual and numerical models that are used to predict or validate the potential radioactive waste containment performance of the system. The concept of performance confirmation for the WIPP is one that has evolved since the first repository work was initiated decades ago and plays an important role in assuring adequate repository performance both now and in the long-term. The WIPP mission has progressed from a pilot project to an operational disposal facility and will progress to eventual site closure when disposal operations are completed. Performance confirmation is an important part of each of these progressions. The concept of disposing radioactive waste in a geologic repository today involves a complete understanding of many technical, political, regulatory, societal and economic elements. Many of these elements overlap and solving all relevant issues necessary to site, operate and decommission a disposal facility should be done with knowledge of each element's requirements and impacts. Performance confirmation is one tool that can help to coordinate many of these elements into a program that actively investigates what is thought to be adequately understood about the system and what information is lacking. A performance confirmation program is used to determine ways to challenge and verify those areas that are thought to be understood and to find ways to understand

  7. Groundwater monitoring plan for the Hanford Site 200 Area Treated Effluent Disposal Facility

    SciTech Connect

    DB Barnett

    2000-05-17

    Seven years of groundwater monitoring at the 200 Area Treated Effluent Disposal Facility (TEDF) have shown that the uppermost aquifer beneath the facility is unaffected by TEDF effluent. Effluent discharges have been well below permitted and expected volumes. Groundwater mounding from TEDF operations predicted by various models has not been observed, and waterlevels in TEDF wells have continued declining with the dissipation of the nearby B Pond System groundwater mound. Analytical results for constituents with enforcement limits indicate that concentrations of all these are below Practical Quantitation Limits, and some have produced no detections. Likewise, other constituents on the permit-required list have produced results that are mostly below sitewide background. Comprehensive geochemical analyses of groundwater from TEDF wells has shown that most constituents are below background levels as calculated by two Hanford Site-wide studies. Additionally, major ion proportions and anomalously low tritium activities suggest that groundwater in the aquifer beneath the TEDF has been sequestered from influences of adjoining portions of the aquifer and any discharge activities. This inference is supported by recent hydrogeologic investigations which indicate an extremely slow rate of groundwater movement beneath the TEDF. Detailed evaluation of TEDF-area hydrogeology and groundwater geochemistry indicate that additional points of compliance for groundwater monitoring would be ineffective for this facility, and would produce ambiguous results. Therefore, the current groundwater monitoring well network is retained for continued monitoring. A quarterly frequency of sampling and analysis is continued for all three TEDF wells. The constituents list is refined to include only those parameters key to discerning subtle changes in groundwater chemistry, those useful in detecting general groundwater quality changes from upgradient sources, or those retained for comparison with end

  8. Grout long radius flow testing to support Saltstone disposal Unit 5 design

    SciTech Connect

    Stefanko, D. B.; Langton, C. A.; Serrato, M. G.; Brooks, T. E. II; Huff, T. H.

    2013-02-24

    The Saltstone Facility, located within the Savannah River Site (SRS) near Aiken, South Carolina, consists of two facility segments: The Saltstone Production Facility (SPF) and the Saltstone Disposal Facility (SDF). The SPF receives decontaminated legacy low level sodium salt waste solution that is a byproduct of prior nuclear material processing. The salt solution is mixed with cementitious materials to form a grout slurry known as “Saltstone”. The grout is pumped to the SDF where it is placed in a Saltstone Disposal Unit (SDU) to solidify. SDU 6 is referred to as a “mega vault” and is currently in the design stage. The conceptual design for SDU 6 is a single cell, cylindrical geometry approximately 114.3 meters in diameter by 13.1 meter high and is larger than previous cylindrical SDU designs, 45.7 meters in diameter by 7.01 meters high (30 million gallons versus 2.9 million gallons of capacity). Saltstone slurry will be pumped into the new waste disposal unit through roof openings at a projected flow rate of about 34.1 cubic meters per hour. Nine roof openings are included in the design to discharge material into the SDU with an estimated grout pour radius of 22.9 to 24.4 meters and initial drop height of 13.1 meters. The conceptual design for the new SDU does not include partitions to limit the pour radius of the grout slurry during placement other than introducing material from different pour points. This paper addresses two technical issues associated with the larger diameter of SDU 6; saltstone flow distance in a tank 114.3 meters in diameter and quality of the grout. A long-radius flow test scaled to match the velocity of an advancing grout front was designed to address these technology gaps. The emphasis of the test was to quantify the flow distance and to collect samples to evaluate cured properties including compressive strength, porosity, density, and saturated hydraulic conductivity. Two clean cap surrogate mixes (saltstone premix plus water

  9. Grout Long Radius Flow Testing to Support Saltstone Disposal Unit 6 Design - 13352

    SciTech Connect

    Stefanko, D.B.; Langton, C.A.; Serrato, M.G.; Brooks, T.E. II; Huff, T.H.

    2013-07-01

    The Saltstone Facility, located within the Savannah River Site (SRS) near Aiken, South Carolina, consists of two facility segments: The Saltstone Production Facility (SPF) and the Saltstone Disposal Facility (SDF). The SPF receives decontaminated legacy low level sodium salt waste solution that is a byproduct of prior nuclear material processing. The salt solution is mixed with cementitious materials to form a grout slurry known as 'Saltstone'. The grout is pumped to the SDF where it is placed in a Saltstone Disposal Unit (SDU) to solidify. SDU 6 is referred to as a 'mega vault' and is currently in the design stage. The conceptual design for SDU 6 is a single cell, cylindrical geometry approximately 114.3 meters in diameter by 13.1 meter high and is larger than previous cylindrical SDU designs, 45.7 meters in diameter by 7.01 meters high (30 million gallons versus 2.9 million gallons of capacity). Saltstone slurry will be pumped into the new waste disposal unit through roof openings at a projected flow rate of about 34.1 cubic meters per hour. Nine roof openings are included in the design to discharge material into the SDU with an estimated grout pour radius of 22.9 to 24.4 meters and initial drop height of 13.1 meters. The conceptual design for the new SDU does not include partitions to limit the pour radius of the grout slurry during placement other than introducing material from different pour points. This paper addresses two technical issues associated with the larger diameter of SDU 6; Saltstone flow distance in a tank 114.3 meters in diameter and quality of the grout. A long-radius flow test scaled to match the velocity of an advancing grout front was designed to address these technology gaps. The emphasis of the test was to quantify the flow distance and to collect samples to evaluate cured properties including compressive strength, porosity, density, and saturated hydraulic conductivity. Two clean cap surrogate mixes (Saltstone premix plus water) were

  10. Compliance matrix for the Mixed Waste Disposal Facilities, Trenches 31 and 34, burial ground 218-W-5. Revision 1

    SciTech Connect

    Carlyle, D.W.

    1994-12-30

    The purpose of the Trench 31 and 34 Mixed Waste Disposal Facility Compliance Matrix is to provide objective evidence of implementation of all regulatory and procedural--institutional requirements for the disposal facilities. This matrix provides a listing of the individual regulatory and procedural--institutional requirements that were addressed. Subject matter experts reviewed pertinent documents that had direct or indirect impact on the facility. Those found to be applicable were so noted and listed in Appendix A. Subject matter experts then extracted individual requirements from the documents deemed applicable and listed them in the matrix tables. The results of this effort are documented in Appendix B. The implementing compliance documentation for WHC-CM manuals is not included in Appendix B because these are, by definition, implementing documents.

  11. Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site

    SciTech Connect

    Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

    1995-03-01

    In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

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

    SciTech Connect

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

    2010-09-01

    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

  13. DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER

    SciTech Connect

    G. Radulesscu; J.S. Tang

    2000-06-07

    The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this analysis is to

  14. Annual Report for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility – Fiscal Year 2015

    SciTech Connect

    French, Sean B.; Stauffer, Philip H.; Birdsell, Kay H.

    2016-02-29

    As a condition to the disposal authorization statement issued to Los Alamos National Laboratory (LANL or the Laboratory) on March 17, 2010, a comprehensive performance assessment and composite analysis maintenance program must be implemented for the Technical Area 54, Area G disposal facility. Annual determinations of the adequacy of the performance assessment and composite analysis (PA/CA) are to be conducted under the maintenance program to ensure that the conclusions reached by those analyses continue to be valid. This report summarizes the results of the fiscal year (FY) 2015 annual review for Area G.

  15. How to Tackle Tough Facility Design Considerations

    ERIC Educational Resources Information Center

    Kalina, David

    2007-01-01

    This article is part of a series that has offered insight on planning a facilities project, hiring professionals, delivery system options and owner's responsibilities. In this article, the author focuses on some of the planning and design concepts one may be asked to consider in providing direction to his design and construction team. These…

  16. Interior Design Factors in Library Facilities.

    ERIC Educational Resources Information Center

    Jackson, Patricia Ann

    When planning the interior of a library facility, the planning team of librarian, library consultant, architect, and interior design consultant must focus attention on the basic principles of interior design and the psychological needs of the user. Colors for an interior should be selected with careful regard to space, light, and emotional and…

  17. Impact of Technology on School Facility Design.

    ERIC Educational Resources Information Center

    North Carolina State Dept. of Public Instruction, Raleigh.

    Computers and other technological innovations are becoming a greater part of today's educational system requiring educational facility designers to plan for their use when designing or renovating new buildings. This booklet considers the building needs for accommodating new technology, particularly focusing on the impact of personal computers and…

  18. Acoustical Design of Music Education Facilities.

    ERIC Educational Resources Information Center

    McCue, Edward, Ed.; Talaske, Richard H., Ed.

    This publication provides essays on the acoustical design of music education facilities and reproductions of posters describing 50 projects presented at the 117th Meeting of the Acoustical Society of American held in Syracuse, New York in May 1989. Essays are as follows: "Introduction to the Design Process" (Richard Talaske); "The…

  19. How to Tackle Tough Facility Design Considerations

    ERIC Educational Resources Information Center

    Kalina, David

    2007-01-01

    This article is part of a series that has offered insight on planning a facilities project, hiring professionals, delivery system options and owner's responsibilities. In this article, the author focuses on some of the planning and design concepts one may be asked to consider in providing direction to his design and construction team. These…

  20. Design Portfolio, 1995. The Educational Facility Planner.

    ERIC Educational Resources Information Center

    The Educational Facility Planner, 1995

    1995-01-01

    This document contains nationally recognized educational-facility designs, including the 1994 James D. MacConnell Award Winner--Heritage Oak Elementary School in Roseville, California. The architectural designs of other schools are also included--10 elementary schools, 6 high schools, 1 vocational school, 3 institutes of higher education, 1…

  1. Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.

    PubMed

    Korucu, M Kemal; Karademir, Aykan

    2014-02-01

    The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place.

  2. Radionuclide migration pathways analysis for the Oak Ridge Central Waste Disposal Facility on the West Chestnut Ridge site

    SciTech Connect

    Pin, F.G.; Witherspoon, J.P.; Lee, D.W.; Cannon, J.B.; Ketelle, R.H.

    1984-10-01

    A dose-to-man pathways analysis is performed for disposal of low-level radioactive waste at the Central Waste Disposal Facility on the West Chestnut Ridge Site. Both shallow land burial (trench) and aboveground (tumulus) disposal methods are considered. The waste volumes, characteristics, and radionuclide concentrations are those of waste streams anticipated from the Oak Ridge National Laboratory, the Y-12 Plant, and the Oak Ridge Gaseous Diffusion Plant. The site capacity for the waste streams is determined on the basis of the pathways analysis. The exposure pathways examined include (1) migration and transport of leachate from the waste disposal units to the Clinch River (via the groundwater medium for trench disposal and Ish Creek for tumulus disposal) and (2) those potentially associated with inadvertent intrusion following a 100-year period of institutional control: an individual resides on the site, inhales suspended particles of contaminated dust, ingests vegetables grown on the plot, consumes contaminated water from either an on-site well or from a nearby surface stream, and receives direct exposure from the contaminated soil. It is found that either disposal method would provide effective containment and isolation for the anticipated waste inventory. However, the proposed trench disposal method would provide more effective containment than tumuli because of sorption of some radionuclides in the soil. Persons outside the site boundary would receive radiation doses well below regulatory limits if they were to ingest water from the Clinch River. An inadvertent intruder could receive doses that approach regulatory limits; however, the likelihood of such intrusions and subsequent exposures is remote. 33 references, 31 figures, 28 tables.

  3. Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong

    NASA Astrophysics Data System (ADS)

    Setiawan, Budi; Mila, Oktri; Safni

    2014-03-01

    Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr+ ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10-2 g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

  4. Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong

    SciTech Connect

    Setiawan, Budi; Mila, Oktri; Safni

    2014-03-24

    Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup −2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

  5. Design and simulation of a neutron facility.

    PubMed

    Studenski, Matthew T; Kearfott, Kimberlee J

    2007-02-01

    State and other regulatory entities require that for any facility housing a particle accelerator the surrounding areas must be restricted to public access unless the dose equivalent rate is less than 0.02 mSv h at 5 cm from any accessible wall surrounding the facility under conditions of maximum radiation output. A Monte Carlo radiation transport simulation code, MCNP5, was used to design a proposed facility to shield two D-T neutron generators and one D-D neutron generator. A number of different designs were simulated, but due to cost and space issues a small concrete cave proved to be the best solution for the shielding problem. With this design, all of the neutron generators could be used and all of the rooms surrounding the neutron facility could be considered unrestricted to public access. To prevent unauthorized access into the restricted area of the neutron facility, light curtains, warning lights, door interlocks, and rope barriers will be built into the facility.

  6. Safety Assessment for the Kozloduy National Disposal Facility in Bulgaria - 13507

    SciTech Connect

    Biurrun, E.; Haverkamp, B.; Lazaro, A.; Miralles, A.; Stefanova, I.

    2013-07-01

    Due to the early decommissioning of four Water-Water Energy Reactors (WWER) 440-V230 reactors at the Nuclear Power Plant (NPP) near the city of Kozloduy in Bulgaria, large amounts of low and intermediate radioactive waste will arise much earlier than initially scheduled. In or-der to manage the radioactive waste from the early decommissioning, Bulgaria has intensified its efforts to provide a near surface disposal facility at Radiana with the required capacity. To this end, a project was launched and assigned in international competition to a German-Spanish consortium to provide the complete technical planning including the preparation of the Intermediate Safety Assessment Report. Preliminary results of operational and long-term safety show compliance with the Bulgarian regulatory requirements. The long-term calculations carried out for the Radiana site are also a good example of how analysis of safety assessment results can be used for iterative improvements of the assessment by pointing out uncertainties and areas of future investigations to reduce such uncertainties in regard to the potential radiological impact. The computer model used to estimate the long-term evolution of the future repository at Radiana predicted a maximum total annual dose for members of the critical group, which is carried to approximately 80 % by C-14 for a specific ingestion pathway. Based on this result and the outcome of the sensitivity analysis, existing uncertainties were evaluated and areas for reasonable future investigations to reduce these uncertainties were identified. (authors)

  7. Disposal Of Irradiated Cadmium Control Rods From The Plumbrook Reactor Facility

    SciTech Connect

    Posivak, E.J.; Berger, S.R.; Freitag, A.A.

    2008-07-01

    Innovative mixed waste disposition from NASA's Plum Brook Reactor Facility was accomplished without costly repackaging. Irradiated characteristic hardware with contact dose rates as high as 8 Sv/hr was packaged in a HDPE overpack and stored in a Secure Environmental Container during earlier decommissioning efforts, awaiting identification of a suitable pathway. WMG obtained regulatory concurrence that the existing overpack would serve as the macro-encapsulant per 40CFR268.45 Table 1.C. The overpack vent was disabled and the overpack was placed in a stainless steel liner to satisfy overburden slumping requirements. The liner was sealed and placed in shielded shoring for transport to the disposal site in a US DOT Type A cask. Disposition via this innovative method avoided cost, risk, and dose associated with repackaging the high dose irradiated characteristic hardware. In conclusion: WMG accomplished what others said could not be done. Large D and D contractors advised NASA that the cadmium control rods could only be shipped to the proposed Yucca mountain repository. NASA management challenged MOTA to find a more realistic alternative. NASA and MOTA turned to WMG to develop a methodology to disposition the 'hot and nasty' waste that presumably had no path forward. Although WMG lead a team that accomplished the 'impossible', the project could not have been completed with out the patient, supportive management by DOE-EM, NASA, and MOTA. (authors)

  8. Utilizing Eisenia andrei to assess the ecotoxicity of platinum mine tailings disposal facilities.

    PubMed

    Jubileus, Mandy T; Theron, Pieter D; van Rensburg, Leon; Maboeta, Mark S

    2013-03-01

    South Africa is an important platinum mining country which results in environmental impacts due to the construction of tailing disposal facilities (TDFs). It is unclear what the effects of ageing are on the ecotoxicity of TDFs and whether it increases or decreases over time. The aim of this study was to determine the ecotoxicity of differently aged TDFs by investigating earthworm (Eisenia andrei) responses viz. growth, reproduction, neutral red retention times (NRRT) and tissue metal concentrations. Further, to evaluate the status of these in terms of a geoaccumulation index (I(geo)), pollution index and integrated pollution index. Results indicated that earthworms showed reduced reproductive success (hatchlings per cocoon) and decreased NRRT in all the sites. Juveniles per cocoon between all of the different treatment groups were; control (2.83 ± 0.54) > site 2 (20 years old; 1.83 ± 0.27) > sites 1 and 3 (40 years old; 1.06 ± 0.15 and 6 years old; 0.88 ± 0.39). This might be ascribed to the elevated levels of Cr (±200 to 1,166 μg g(-1)) and Ni (±100 to 316 μg g(-1)) in all of the sites. Earthworms did not bioaccumulate metals with bioconcentration factors for all the different treatments <0.01. Studies like these could be useful when establishing a ranking of TDFs in the future to provide legislative institutions with an indication of the environmental liabilities of platinum mines.

  9. Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Pierce, Eric M.; McGrail, B. Peter; Rodriguez, Elsa A.; Schaef, Herbert T.; Saripalli, Prasad; Serne, R. Jeffrey; Krupka, Kenneth M.; Martin, P. F.; Baum, Steven R.; Geiszler, Keith N.; Reed, Lunde R.; Shaw, Wendy J.

    2004-09-01

    This data package documents the experimentally derived input data on the representative waste glasses; LAWA44, LAWB45, and LAWC22. This data will be used for Subsurface Transport Over Reactive Multi-phases (STORM) simulations of the Integrated Disposal Facility (IDF) for immobilized low-activity waste (ILAW). The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in July 2005. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali (Na+)-hydrogen (H+) ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow (PUF) and product consistency (PCT) tests where used for accelerated weathering or aging of the glasses in order to determine a chemical reaction network of secondary phases that form. The majority of the thermodynamic data used in this data package were extracted from the thermody-namic database package shipped with the geochemical code EQ3/6, version 8.0. Because of the expected importance of 129I release from secondary waste streams being sent to IDF from various thermal treatment processes, parameter estimates for diffusional release and solubility-controlled release from cementitious waste forms were estimated from the available literature.

  10. Annual Groundwater Detection Monitoring Report for the Idaho CERCLA Disposal Facility (2008)

    SciTech Connect

    Cahn, Lorie

    2009-07-31

    This report presents the data collected for groundwater detection monitoring at the Idaho Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Disposal Facility (ICDF) during calendar year 2008. The detection-monitoring program developed for the ICDF groundwater-monitoring wells is applicable to six wells completed in the uppermost portion of the Snake River Plain Aquifer - five wells downgradient of the ICDF and one well upgradient. The ICDF detection-monitoring program was established to meet the substantive requirements of Title 40 Code of Federal Regulations (CFR) Parts 264.97 and 264.98, which are applicable or relevant and appropriate requirements under CERCLA. Semiannual groundwater samples were collected and analyzed for indicator parameters in March and September. The indicator parameters focus on constituents that are found in higher concentrations in ICDF leachate than in groundwater (bicarbonate alkalinity, sulfate, U-233, U-234, and U-238). The only detection monitoring limits that were exceeded were for bicarbonate alkalinity. Bicarbonate alkalinity is naturally occurring in groundwater. Bicarbonate alkalinity found in ICDF detection monitoring wells is not a result of waste migration from the ICDF landfill or the evaporation pond. The U.S. Department of Energy will continue with detection monitoring for the ICDF, which is semiannual sampling for indicator parameters.

  11. Annual Groundwater Detection Monitoring Report for the Idaho CERCLA Disposal Facility (2008)

    SciTech Connect

    Lorie Cahn

    2009-07-31

    This report presents the data collected for groundwater detection monitoring at the Idaho Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Disposal Facility (ICDF) during calendar year 2008. The detection-monitoring program developed for the ICDF groundwater-monitoring wells is applicable to six wells completed in the uppermost portion of the Snake River Plain Aquifer. Five wells downgradient of the ICDF and one well upgradient. The ICDF detection-monitoring program was established to meet the substantive requirements of Title 40 Code of Federal Regulations (CFR) Parts 264.97 and 264.98, which are applicable or relevant and appropriate requirements under CERCLA. Semiannal groundwater samples were collected and analyzed for indicator parameters in March and September. The indicator parameters focus on constituents that are found in higher concentrations in ICDF leachate than in groundwater (bicarbonate alkalinity, sulfate, U-233, and U-238). The only detection monitoring limits that were exceeded were for bicarbonate alkalinity. Bicarbonate alkalinity is naturally occuring in groundwater. Bicarbonate alkalinity found in ICDF detection monitoring wells is not a result of waste migration from the ICDF landfill or the evaporation pond. The U.S. Department of Energy will continue with detection monitoring for the ICDF, which is semiannual sampling for indicator parameters.

  12. Closure of a hazardous waste disposal facility in an active oil field

    SciTech Connect

    Knott, S.A.; White, A.E. )

    1991-02-01

    State and federal laws and regulations enacted during the past five years have led to closure activities at a large number of hazardous waste disposal facilities. These closures are often lengthy, difficult, and expensive. Closures must adhere to federal regulations promulgated by the U.S. Environmental Protection Agency (EPA) as well as State regulations administered by the Department of Health Services and the Regional Water Quality Control Boards. This exhibit depicts the regulatory framework for closure of a hazardous waste site. It also describes the closure alternatives for a site in the Central Valley which primarily accepted wastes generated from oil field activities. Generally, one of two closure alternatives is followed: (1) sites are closed-in-place with the wastes covered or monitored, or (2) wastes are treated and removed so that no waste or waste residue remains. Regulations issued by the EPA in 1987 made another option available. This option is risk-based clean closure and involves the identification of risk-based cleanup goals. A site-specific risk assessment adhering to federal and state guidelines is required to establish the cleanup goals. Waste constituents present in concentrations below these goals may be left in place without post closure care.

  13. Recent progress in siting low-level waste disposal facilities in the Southwestern Compact and the Central Interstate Compact

    SciTech Connect

    DeOld, J.H.; Shaffner, J.A.

    1995-11-01

    US Ecology is the private contractor selected to develop and operate low-level waste disposal facilities in the Southwestern and the Central Interstate Compacts. These initiatives have been proceeding for almost a decade in somewhat different regulatory and political climates. This paper chronicles recent events in both projects. In both cases there is reason for continued optimism that low-level waste facilities to serve the needs of waste generators in these two compacts will soon be a reality. When the California Department of Health Services issued a license for the proposed Ward Valley LLRW disposal facility on September 16, 1993, it represented a significant step in implementation of a new generation of regional LLRW disposal facilities. While limited scope land transfer hearings were on the horizon, project beneficiaries were confident that the disposal site would be operational by 1995. Since then, however, political initiatives championed by Senator Barbara Boxer (D-CA) have clouded the federal land transfer process and left the commencement date of operations indeterminant. Since 1993, the biomedical community, waste generators most affected by delays, have been petitioning the current administration to emphasize the need for a timely solution. These efforts are aimed at Clinton administration officials responsible for current delays, who apparently have not recognized the importance of the Ward Valley facility to California`s economy, nor the national ramifications of their delaying actions. The current status of challenges to the Ward Valley license and California Environmental Quality Act (CEQA) documentation is also provided. The presentation also discusses the recently completed National Academy of Science evaluation of reports critical of the Ward Valley development process.

  14. An Integrated Facility for Municipal Solid Waste Disposal, Electrical Generation, and Desalination.

    DTIC Science & Technology

    1995-01-01

    A preliminary design was completed for a facility that uses municipal solid waste as file for generating electricity and cogeneration steam for a... municipal solid waste will provide nearly 2% of per capita electrical power needs and 7% of fresh water requirements. This thesis proposes a new arrangement... Municipal Solid Waste . Developing new power plant sources for electrical generation now requires searching for scarce energy resources and regularly

  15. Linkage Between Post-Closure Safety Case Review and the Authorization Process for Radioactive Waste Disposal Facilities

    SciTech Connect

    Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.; Bennett, D. G.

    2003-02-27

    The Environment Agency (the Agency) has responsibilities under the Radioactive Substances Act of 1993 for regulating the disposal and storage of radioactive wastes in England and Wales, including regulation of the disposal site for UK solid low-level waste (LLW) at Drigg in Cumbria, NW England. To help inform the next review of the Drigg disposal authorization, the Agency has required the operator, British Nuclear Fuels plc to submit a Post-Closure Safety Case which will assess the potential long-term impacts from the site. With the aim of using best practice to determine authorization conditions, the Agency contracted Galson Sciences, Ltd to undertake an international survey of authorization procedures for comparable facilities in other countries. This paper provides an overview of the findings from the international survey.

  16. Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

    SciTech Connect

    Hladek, K.L.

    1997-10-07

    The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

  17. Transparent tools for uncertainty analysis in high level waste disposal facilities safety

    SciTech Connect

    Lemos, Francisco Luiz de; Helmuth, Karl-Heinz; Sullivan, Terry

    2007-07-01

    In this paper some results of a further development of a technical cooperation project, initiated in 2004, between the CDTN/CNEN, The Brazilian National Nuclear Energy Commission, and the STUK, The Finnish Radiation and Nuclear Safety Authority, are presented. The objective of this project is to study applications of fuzzy logic, and artificial intelligence methods, on uncertainty analysis of high level waste disposal facilities safety assessment. Uncertainty analysis is an essential part of the study of the complex interactions of the features, events and processes, which will affect the performance of the HLW disposal system over the thousands of years in the future. Very often the development of conceptual and computational models requires simplifications and selection of over conservative parameters that can lead to unrealistic results. These results can mask the existing uncertainties which, consequently, can be an obstacle to a better understanding of the natural processes. A correct evaluation of uncertainties and their rule on data interpretation is an important step for the improvement of the confidence in the calculations and public acceptance. This study focuses on dissolution (source), solubility and sorption (sink) as key processes for determination of release and migration of radionuclides. These factors are affected by a number of parameters that characterize the near and far fields such as pH; temperature; redox conditions; and other groundwater properties. On the other hand, these parameters are also consequence of other processes and conditions such as water rock interaction; pH and redox buffering. Fuzzy logic tools have been proved to be suited for dealing with interpretation of complex, and some times conflicting, data. For example, although some parameters, such as pH and carbonate, are treated as independent, they have influence in each other and on the solubility. It is used the technique of fuzzy cognitive mapping is used for analysis of

  18. FFTF disposable solid waste cask

    SciTech Connect

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

    1983-01-01

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

  19. Ground-water quality near the northwest 58th Street solid-waste disposal facility, Dade County, Florida

    USGS Publications Warehouse

    Mattraw, H.C.; Hull, John E.; Klein, Howard

    1978-01-01

    The Northwest 58th Street solid-waste disposal facility, 3 miles west of a major Dade County municipal water-supply well field, overlays the Biscayne aquifer, a permeable, solution-riddled limestone which transmits leachates eastward at a calculated rate of 2.9 feet per day. A discrete, identifiable leachate plume has been recognized under and downgradient from the waste disposal facility. Concentrations of sodium, ammonia, and dissolved solids decreased with depth beneath the disposal area and downgradient in response to an advective and convective dispersion. At a distance of about one-half downgradient, the rate of contribution of leachate from the source to the leading edge of the plume was about equal to the rate of loss of leachate from the leading edge of the plume by diffusion and dilution by rainfall infiltration during the period August 1973 - July 1975. Heavy metals and pesticides are filtered, adsorbed by aquifer materials, or are precipitated near the disposal area. (Woodard-USGS)

  20. The potential for criticality following disposal of uranium at low-level waste facilities: Uranium blended with soil

    SciTech Connect

    Toran, L.E.; Hopper, C.M.; Naney, M.T.

    1997-06-01

    The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop achievable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM), and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team`s approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some achievable scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via sorption or precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits. The analysis of SNM was restricted to {sup 235}U in the present scope of work. The outcome of the work indicates that criticality is possible given established regulatory limits on SNM disposal. However, a review based on actual disposal records of an existing site operation indicates that the potential for criticality is not a concern under current burial practices.

  1. Preliminary design for a maglev development facility

    SciTech Connect

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. ); Zhang, Z.Y. ); Myers, G.; Cvercko, A. ); Williams, J.R. )

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  2. Performance assessment and licensing issues for United States commercial near-surface low-level radioactive waste disposal facilities

    SciTech Connect

    Birk, S.M.

    1997-10-01

    The final objective of performance assessment for a near-surface LLW disposal facility is to demonstrate that potential radiological impacts for each of the human exposure pathways will not violate applicable standards. This involves determining potential pathways and specific receptor locations for human exposure to radionuclides; developing appropriate scenarios for each of the institutional phases of a disposal facility; and maintaining quality assurance and control of all data, computer codes, and documentation. The results of a performance assessment should be used to demonstrate that the expected impacts are expected to be less than the applicable standards. The results should not be used to try to predict the actual impact. This is an important distinction that results from the uncertainties inherent in performance assessment calculations. The paper discusses performance objectives; performance assessment phases; scenario selection; mathematical modeling and computer programs; final results of performance assessments submitted for license application; institutional control period; licensing issues; and related research and development activities.

  3. Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal

    SciTech Connect

    R. A. Montgomery

    2008-05-01

    This Toxic Substances Control Act Risk-Based Polychlorinated Biphenyl Disposal plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex, Idaho National Laboratory Site, to address painted surfaces in the empty canal under 40 CFR 761.62(c) for paint, and under 40 CFR 761.61(c) for PCBs that may have penetrated into the concrete. The canal walls and floor will be painted with two coats of contrasting non-PCB paint and labeled as PCB. The canal is covered with open decking; the access grate is locked shut and signed to indicate PCB contamination in the canal. Access to the canal will require facility manager permission. Protective equipment for personnel and equipment entering the canal will be required. Waste from the canal, generated during ultimate Decontamination and Decommissioning, shall be managed and disposed as PCB Bulk Product Waste.

  4. Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

    SciTech Connect

    Collard, L.B.

    2000-09-26

    This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.

  5. Harold P. Geerdes on Musical Facility Design.

    ERIC Educational Resources Information Center

    Wagner, Michael

    1996-01-01

    Presents an interview with Dr. Harold P. Geerdes, world-renowned music facility planner, acoustician, and music professor. Dr. Geerdes discusses the different characteristics of rehearsal spaces and concert halls as well as the importance of interior materials and design. He also provides some easy and inexpensive tips for schools. (MJP)

  6. Earth integrated design: office dormitory facility

    SciTech Connect

    Shapira, H. B.; Barnes, P. R.

    1980-01-01

    The generation process of the design of the Joint Institute for Heavy Ion Research is described. Architectural and energy considerations are discussed. The facility will contain living quarters for guest scientists who come to Oak Ridge to conduct short experiments and sleeping alcoves for local researchers on long experimental shifts as well as office space. (MHR)

  7. Facility Design as an Agent of Learning

    ERIC Educational Resources Information Center

    Subel, Sue

    2007-01-01

    This article discusses the importance of designing a library media center that engages students in constructing new knowledge. The author describes the planning stages of a new library facility. In the early planning stages, the author focused on the expectations of the administration. She soon realized that they had included all the…

  8. Designing Tennis Facilities to Minimize Vandalism.

    ERIC Educational Resources Information Center

    Davis, Robert E.

    1987-01-01

    Suggestions are presented for designing indoor and outdoor tennis facilities that will inhibit vandalism. Recommendations include using high-quality materials that will be difficult to damage, adopting and posting rules for court use, and constructing self-contained power sources. (CB)

  9. Cold vacuum drying facility 90% design review

    SciTech Connect

    O`Neill, C.T.

    1997-05-02

    This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage.

  10. Trace elements in soil and biota in confined disposal facilities for dredged material.

    PubMed

    Beyer, W N; Miller, G; Simmers, J W

    1990-01-01

    We studied the relation of trace element concentrations in soil to those in house mice (Mus musculus), common reed (Phragmites australis) and ladybugs (Coccinella septempunctata at five disposal facilities for dredged material. The sites had a wide range of soil trace element concentrations, acid soils and a depauperate fauna. They were very poor wildlife habitat because they were dominated by the common reed. Bioassay earthworms exposed to surface soils from three of the five sites died, whereas those exposed to four of five soils collected a meter deep survived, presumably because the deeper, unoxidized soil, was not as acid. Concentrations of Ni and Cr in the biota from each of the sites did not seem to be related to the concentrations of the same elements in soil. Although Pb, Zn and Cu concentrations in biota were correlated with those in soil, the range of concentrations in the biota was quite small compared to that in soil. The concentrations of Pb detected in mice were about as high as the concentrations previously reported in control mice from other studies. Mice from the most contaminated site (530 ppm Pb in soil) contained only slightly more Pb (8 ppm dry wt) than did mice (2-6 ppm dry wt) from sites containing much less Pb (22-92 ppm in soil). Despite the acid soil conditions, very little Cd was incorporated into food chains. Rather, Cd was leaching from the surface soil. We concluded that even the relatively high concentrations of trace elements in the acid dredged material studied did not cause high concentrations of trace elements in the biota.

  11. Trace elements in soil and biota in confined disposal facilities for dredged material

    USGS Publications Warehouse

    Beyer, W.N.; Miller, G.; Simmers, J.W.

    1990-01-01

    We studied the relation of trace element concentrations in soil to those in house mice (Mus musculus), common reed (Phragmites australis) and ladybugs (Coccinella septempunctata) at five disposal facilities for dredged material. The sites had a wide range of soil trace element concentrations, acid soils and a depauperate fauna. They were very poor wildlife habitat because they were dominated by the common reed. Bioassay earthworms exposed to surface soils from three of the five sites died, whereas those exposed to four of five soils collected a meter deep survived, presumably because the deeper, unoxidized soil, was not as acid. Concentrations of Ni and Cr in the biota from each of the sites did not seem to be related to the concentrations of the same elements in soil. Although Pb, Zn and Cu concentrations in biota were correlated with those in soil, the range of concentrations in the biota was quite small compared to that in soil. The concentrations of Pb detected in mice were about as high as the concentrations previously reported in control mice from other studies. Mice from the most contaminated site (530 ppm Pb in soil) contained only slightly more Pb (8 ppm dry wt) than did mice (2-6 ppm dry wt) from sites containing much less Pb (22-92 ppm in soil). Despite the acid soil conditions, very little Cd was incorporated into food chains. Rather, Cd was leaching from the surface soil. We concluded that even the relatively high concentrations of trace elements in the acid dredged material studied did not cause high, concentrations of trace elements in the biota.

  12. Gemini enclosure and support facility design philosophy and design description

    NASA Astrophysics Data System (ADS)

    Raybould, Keith; Ford, Robert M.; Gillett, Paul E.; Hardash, Steven G.; Pentland, Gordon

    1994-06-01

    The Gemini project is an international collaboration between the USA, United Kingdom, Canada, Chile, Argentina, and Brazil, to design, fabricate and assemble two 8 M telescopes, one on Mauna Kea in Hawaii, the other on Cerro Pachon in Chile. The telescopes will be national facilities designed to meet the Gemini Science Requirements, a document developed by the Gemini Science Committee. This paper describes the design considerations that influence the scientific performance of the enclosure and support facility, and the features that have been incorporated to meet the demanding science requirements, particularly the 0.026 arc sec allowance for `enclosure seeing'. A description of the Gemini enclosure, support facilities and site plans for Mauna Kea is given here together with a brief description of the analysis and testing that has been performed to establish the performance of the facility.

  13. Project C-018H, 242-A Evaporator/PUREX Plant Process Condensate Treatment Facility, functional design criteria. Revision 3

    SciTech Connect

    Sullivan, N.

    1995-05-02

    This document provides the Functional Design Criteria (FDC) for Project C-018H, the 242-A Evaporator and Plutonium-Uranium Extraction (PUREX) Plant Condensate Treatment Facility (Also referred to as the 200 Area Effluent Treatment Facility [ETF]). The project will provide the facilities to treat and dispose of the 242-A Evaporator process condensate (PC), the Plutonium-Uranium Extraction (PUREX) Plant process condensate (PDD), and the PUREX Plant ammonia scrubber distillate (ASD).

  14. Public perception of odour and environmental pollution attributed to MSW treatment and disposal facilities: a case study.

    PubMed

    De Feo, Giovanni; De Gisi, Sabino; Williams, Ian D

    2013-04-01

    If residents' perceptions, concerns and attitudes towards waste management facilities are either not well understood or underestimated, people can produce strong opposition that may include protest demonstrations and violent conflicts such as those experienced in the Campania Region of Italy. The aim of this study was to verify the effects of the closure of solid waste treatment and disposal facilities (two landfills and one RDF production plant) on public perception of odour and environmental pollution. The study took place in four villages in Southern Italy. Identical questionnaires were administered to residents during 2003 and after the closure of the facilities occurred in 2008. The residents' perception of odour nuisance considerably diminished between 2003 and 2009 for the nearest villages, with odour perception showing an association with distance from the facilities. Post closure, residents had difficulty in identifying the type of smell due to the decrease in odour level. During both surveys, older residents reported most concern about the potentially adverse health impacts of long-term exposure to odours from MSW facilities. However, although awareness of MSW facilities and concern about potentially adverse health impacts varied according to the characteristics of residents in 2003, substantial media coverage produced an equalisation effect and increased knowledge about the type of facilities and how they operated. It is possible that residents of the village nearest to the facilities reported lower awareness of and concern about odour and environmental pollution because the municipality received economic compensation for their presence.

  15. Design considerations for mental health facilities.

    PubMed

    Willis, V J

    1980-07-01

    The design environment of mental health facilities can facilitate the human interactions essential to treatment and can help in meeting clients' basic needs for safety and security, for self-esteem, and for the development of interpersonal and social skills. To determine the factors in the design of interior spaces that optimize clients' response to therapy, the author made a study of six Indiana community mental health centers. Drawing on that study and other sources, she presents design recommendations for mental health facilities for such areas as reception and admission areas, corridors and stairwells, therapists' offices, inpatient rooms, and dayrooms. Other discussions cover the relation of color, visual patterning, and light, and the selection of materials and finishes.

  16. Enforcement Alert: Hazardous Waste Management Practices at Mineral Processing Facilities Under Scrutiny by U.S. EPA; EPA Clarifies 'Bevill Exclusion' Wastes and Establishes Disposal Standards

    EPA Pesticide Factsheets

    This is the enforcement alert for Hazardous Waste Management Practices at Mineral Processing Facilities Under Scrutiny by U.S. EPA; EPA Clarifies 'Bevill Exclusion' Wastes and Establishes Disposal Standards

  17. Notification: EPA Progress on Meeting Resource Conservation and Recovery Act Statutory Mandate for Minimum Frequency of Inspections at Hazardous Waste Disposal Facilities

    EPA Pesticide Factsheets

    Project #OPE-FY15-0018, January 20, 2015. The EPA OIG plans to begin preliminary research on EPA’s progress in meeting minimum inspection requirements under the RCRA at treatment, storage and disposal facilities (TSDFs).

  18. Hazardous Waste Treatment, Storage, and Disposal Facilities-Organic Air Emission Standards for Process Vents and Equipment Leaks - Technical Amendment - Federal Register Notice, April 26, 1991

    EPA Pesticide Factsheets

    This document corrects typographical errors in the regulatory text of the final standards that would limit organic air emissions as a class at hazardous waste treatment, storage, and disposal facilities (TSDF) that are subject to regulation under subtitle

  19. Geohydrologic evaluation for the 200 Area Effluent Treatment Facility State-Approved Land Disposal Site: Addendum to WAC 173-240 Engineering Report

    SciTech Connect

    Ballantyne, N.A.

    1993-08-01

    This document provides a geohydrologic evaluation for the disposal of liquid effluent from the 200 Area Effluent Treatment Facility (ETF) at the Hanford Site. This work forms an addendum to the engineering report that supports the completion of the ETF.

  20. Conceptual design of the National Ignition Facility

    SciTech Connect

    Paisner, J.A.; Kumpan, S.A.; Lowdermilk, W.H.; Boyes, J.D.; Sorem, M.

    1995-08-02

    DOE commissioned a Conceptual Design Report (CDR) for the National Ignition Facility (NIF) in January 1993 as part of a Key Decision Zero (KDO), justification of Mission Need. Motivated by the progress to date by the Inertial Confinement Fusion (ICF) program in meeting the Nova Technical Contract goals established by the National Academy of Sciences in 1989, the Secretary requested a design using a solid-state laser driver operating at the third harmonic (0.35 {mu}m) of neodymium (Nd) glass. The participating ICF laboratories signed a Memorandum of Agreement in August 1993, and established a Project organization, including a technical team from the Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the Laboratory for Laser Energetics at the University of Rochester. Since then, we completed the NIF conceptual design, based on standard construction at a generic DOE Defense Program`s site, and issued a 7,000-page, 27-volume CDR in May 1994.2 Over the course of the conceptual design study, several other key documents were generated, including a Facilities Requirements Document, a Conceptual Design Scope and Plan, a Target Physics Design Document, a Laser Design Cost Basis Document, a Functional Requirements Document, an Experimental Plan for Indirect Drive Ignition, and a Preliminary Hazards Analysis (PHA) Document. DOE used the PHA to categorize the NIF as a low-hazard, non-nuclear facility. On October 21, 1994 the Secretary of Energy issued a Key Decision One (KD1) for the NIF, which approved the Project and authorized DOE to request Office of Management and Budget-approval for congressional line-item FY 1996 NIF funding for preliminary engineering design and for National Environmental Policy Act activities. In addition, the Secretary declared Livermore as the preferred site for constructing the NIF. The Project will cost approximately $1.1 billion and will be completed at the end of FY 2002.

  1. Public perception of odour and environmental pollution attributed to MSW treatment and disposal facilities: A case study

    SciTech Connect

    De Feo, Giovanni; De Gisi, Sabino; Williams, Ian D.

    2013-04-15

    Highlights: ► Effects of closing MSW facilities on perception of odour and pollution studied. ► Residents’ perception of odour nuisance considerably diminished post closure. ► Odour perception showed an association with distance from MSW facilities. ► Media coverage increased knowledge about MSW facilities and how they operate. ► Economic compensation possibly affected residents’ views and concerns. - Abstract: If residents’ perceptions, concerns and attitudes towards waste management facilities are either not well understood or underestimated, people can produce strong opposition that may include protest demonstrations and violent conflicts such as those experienced in the Campania Region of Italy. The aim of this study was to verify the effects of the closure of solid waste treatment and disposal facilities (two landfills and one RDF production plant) on public perception of odour and environmental pollution. The study took place in four villages in Southern Italy. Identical questionnaires were administered to residents during 2003 and after the closure of the facilities occurred in 2008. The residents’ perception of odour nuisance considerably diminished between 2003 and 2009 for the nearest villages, with odour perception showing an association with distance from the facilities. Post closure, residents had difficulty in identifying the type of smell due to the decrease in odour level. During both surveys, older residents reported most concern about the potentially adverse health impacts of long-term exposure to odours from MSW facilities. However, although awareness of MSW facilities and concern about potentially adverse health impacts varied according to the characteristics of residents in 2003, substantial media coverage produced an equalisation effect and increased knowledge about the type of facilities and how they operated. It is possible that residents of the village nearest to the facilities reported lower awareness of and concern about

  2. Resource Conservation and Recovery Act Training Module about Treatment, Storage and Disposal Facilities

    EPA Pesticide Factsheets

    This training module describes:general requirements applicable to treatment, storage, and disposal facilitiesrequirements for waste analysis and personnel training purpose of a contingency plan and list the emergency notification procedures.

  3. Excess Facilities: DOD Needs More Complete Information and a Strategy to Guide Its Future Disposal Efforts

    DTIC Science & Technology

    2011-09-01

    Disposal Efforts 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR (S) 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER...8 40 U.S.C. § 102(3). 9 DOD has delegated authority to dispose of properties located at military...the State Historic Preservation Officer, among others, to consider a method to best preserve the historic value of the property prior to authorizing

  4. The Influence of Building Codes on Recreation Facility Design.

    ERIC Educational Resources Information Center

    Morrison, Thomas A.

    1989-01-01

    Implications of building codes upon design and construction of recreation facilities are investigated (national building codes, recreation facility standards, and misperceptions of design requirements). Recreation professionals can influence architectural designers to correct past deficiencies, but they must understand architectural and…

  5. Ground-water flow and transport modeling of the NRC-licensed waste disposal facility, West Valley, New York

    SciTech Connect

    Kool, J.B.; Wu, Y.S. )

    1991-10-01

    This report describes a simulation study of groundwater flow and radionuclide transport from disposal at the NRC licensed waste disposal facility in West Valley, New York. A transient, precipitation driven, flow model of the near-surface fractured till layer and underlying unweathered till was developed and calibrated against observed inflow data into a recently constructed interceptor trench for the period March--May 1990. The results suggest that lateral flow through the upper, fractured till layer may be more significant than indicated by previous, steady state flow modeling studies. A conclusive assessment of the actual magnitude of lateral flow through the fractured till could however not be made. A primary factor contributing to this uncertainty is the unknown contribution of vertical infiltration through the interceptor trench cap to the total trench inflow. The second part of the investigation involved simulation of the migration of Sr-90, Cs-137 and Pu-239 from the one of the fuel hull disposal pits. A first-order radionuclide leach rate with rate coefficient of 10{sup {minus}6}/day was assumed to describe radionuclide release into the disposal pit. The simulations indicated that for wastes buried below the fractured till zone, no significant migration would occur. However, under the assumed conditions, significant lateral migration could occur for radionuclides present in the upper, fractured till zone. 23 refs., 68 figs., 12 tabs.

  6. Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

    NASA Astrophysics Data System (ADS)

    Fako, R.; Barariu, Gh.; Toma, R.; Georgescu, R.; Sociu, F.

    2013-07-01

    Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa), to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module) where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

  7. National Ignition Facility design, performance, and cost

    SciTech Connect

    Hogan, W.J.; Paisner, J.A.; Lowdermilk, W.H.

    1994-09-16

    A conceptual design for the National Ignition Facility (NIF) has been completed and its cost has been estimated by a multilaboratory team. To maximize the performance/cost ratio a compact, segmented amplifier is used in a multipass architecture. Many recent optical and laser technology developments have been incorporated into the final design. The Beamlet project has successfully demonstrated the new concept. The mission of ICF Program using the NEF is to achieve ignition and gain in the laboratory. The facility will be used for defense applications such as weapons physics and weapons effects experiments, and for civilian applications such as inertial fusion energy development and fundamental studies of matter at high energy density.

  8. Canister Design for Deep Borehole Disposal of Nuclear Waste

    DTIC Science & Technology

    2006-05-01

    Transportation (DOT), the Nuclear Regulatory Commission (NRC), and the Environmental Protection Agency ( EPA ). DOT regulations specify...approval of packaging and shipping procedures The EPA regulations set limits on radiation doses allowed for members of the public and the amount of...radioactive material introduced by nuclear facilities into the environment. The following are the EPA regulations: Table 1-3. Environmental

  9. Saltstone Disposal Facility Closure Cap Configuration and Degradation Base Case: Institutional Control to Pine Forest Scenario

    SciTech Connect

    Phifer, M.A.

    2004-03-19

    The Performance Assessment (PA) for the Saltstone Disposal Facility (SDF) is currently under revision. As part of the PA revision and as documented herein, the closure cap configuration has been reevaluated and closure cap degradation mechanisms and their impact upon infiltration through the closure cap have been evaluated for the institutional control to pine forest, land use scenario. This land use scenario is considered the base case land use scenario. This scenario assumes a 100-year institutional control period following final SDF closure during which the closure cap is maintained. At the end of institutional control, it is assumed that a pine forest succeeds the cap's original bamboo cover. Infiltration through the upper hydraulic barrier layer of the closure cap as determined by this evaluation will be utilized as the infiltration input to subsequent PORFLOW vadose zone contaminant transport modeling, which will also be performed as part of the PA revision. The impacts of pine forest succession, erosion, and colloidal clay migration as degradation mechanisms on the hydraulic properties of the closure cap layers over time have been estimated and the resulting infiltration through the closure cap has been evaluated. The primary changes caused by the degradation mechanisms that result in increased infiltration are the formation of holes in the upper GCL by pine forest succession and the reduction in the saturated hydraulic conductivity of the drainage layers due to colloidal clay migration into the layers. Erosion can also result in significant increases in infiltration if it causes the removal of soil layers, which provide water storage for the promotion of evapotranspiration. For this scenario, infiltration through the upper GCL was estimated at approximately 0.29 inches/year under initial intact conditions, it increased to approximately 11.6 inches/year at year 1000 in nearly a linear fashion, and it approached an asymptote of around 14.1 inches/year at year

  10. ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY

    SciTech Connect

    Smith, F.; Phifer, M.

    2014-04-10

    A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the

  11. Parallel machine architecture and compiler design facilities

    NASA Technical Reports Server (NTRS)

    Kuck, David J.; Yew, Pen-Chung; Padua, David; Sameh, Ahmed; Veidenbaum, Alex

    1990-01-01

    The objective is to provide an integrated simulation environment for studying and evaluating various issues in designing parallel systems, including machine architectures, parallelizing compiler techniques, and parallel algorithms. The status of Delta project (which objective is to provide a facility to allow rapid prototyping of parallelized compilers that can target toward different machine architectures) is summarized. Included are the surveys of the program manipulation tools developed, the environmental software supporting Delta, and the compiler research projects in which Delta has played a role.

  12. Steam plant ash disposal facility and industrial landfill at the Y-12 Plant, Anderson County, Tennessee. Environmental Assessment

    SciTech Connect

    Not Available

    1992-02-01

    The US Department of Energy (DOE) is proposing to install a wet ash handling system to dewater bottom ash from the coal-fired steam plant at its Y-12 Plant and to construct a new landfill for disposal of industrial wastes, including the dewatered bottom ash. The DOE operates three major facilities on its Oak Ridge Reservation (ORR). Operation of these facilities results in the production of a variety of nonhazardous, nonradioactive solid wastes (approximately 300 m{sup 3} per day, compacted) including sanitary wastes, common industrial wastes and construction debris. At the current rate of use, this existing landfill will be filled within approximately 18 months, and more space is urgently needed. In an effort to alleviate this problem, DOE and WMD management propose to create additional landfill facilities at a nearby site. The potential environmental impacts associated with this proposed action are the subject of this environmental assessment (EA).

  13. Genotoxic effects and serum abnormalities in residents of regions proximal to e-waste disposal facilities in Jinghai, China.

    PubMed

    Li, KeQiu; Liu, ShaSha; Yang, QiaoYun; Zhao, YuXia; Zuo, JunFang; Li, Ran; Jing, YaQing; He, XiaoBo; Qiu, XingHua; Li, Guang; Zhu, Tong

    2014-07-01

    Electronic waste (e-waste) disposal is a growing problem in China, and its effects on human health are a concern. To determine the concentrations of pollutants in peripheral blood and genetic aberrations near an e-waste disposal area in Jinghai, China, blood samples were collected from 30 (age: 41±11.01 years) and 28 (age: 33±2.14 years) individuals residing within 5 and 40km of e-waste disposal facilities in Jinghai (China), respectively, during the week of October 21-28, 2011. Levels of inorganic pollutants (calcium, copper, iron, lead, magnesium, selenium, and zinc) and malondialdehyde (MDA), identities of persistent organic pollutants (POPs), micronucleus rates, and lymphocyte subsets were analyzed in individuals. Total RNA expression profiles were analyzed by group and gender. The population group living in proximity to the e-waste site displayed significantly higher mean levels of copper, zinc, lead, MDAs, POPs (B4-6DE, B7-9DE, total polychlorinated biphenyls, and BB-153). In addition, micronucleus rates of close-proximity group were higher compared with the remote group (18.27% vs. 7.32%). RNA expression of genes involved in metal ion binding and transport, oxidation/reduction, immune defense, and tumorigenesis varied between groups, with men most detrimentally affected (p<0.05). CD4(+)/CD8(+)T cell ratios, CD4(+)CD25(nt/hi)CD127(lo)regulatory T cell percentages, and CD95 expression were greater in the e-waste group (p<0.05). Residing in close proximity to e-waste disposal facilities (≤5km) may be associated with the accumulation of potentially harmful inorganic/organic compounds and gender-preferential genetic aberrations. Copyright © 2014 Elsevier Inc. All rights reserved.

  14. 42 CFR 9.4 - Physical facility policies and design.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Physical facility policies and design. 9.4 Section... policies and design. (a) What standards apply to the facility design and physical plant? The chimpanzee sanctuary facility must be designed to provide sufficient space and variety of natural or artificial...

  15. Engineering safety evaluation for 22 ton steel disposal box lifting bail design

    SciTech Connect

    BOEHNKE, W.M.

    1999-11-23

    The objective of this analysis is to design and analyze the lifting bail of the 22 Ton Steel Waste Disposal Box (SWDB). The new design takes the original lifting bail and adds a hinge allowing the top portion of the bail to fold over towards the lid.

  16. JPL Facilities and Software for Collaborative Design: 1994 - Present

    NASA Technical Reports Server (NTRS)

    DeFlorio, Paul A.

    2004-01-01

    The viewgraph presentation provides an overview of the history of the JPL Project Design Center (PDC) and, since 2000, the Center for Space Mission Architecture and Design (CSMAD). The discussion includes PDC objectives and scope; mission design metrics; distributed design; a software architecture timeline; facility design principles; optimized design for group work; CSMAD plan view, facility design, and infrastructure; and distributed collaboration tools.

  17. Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

    SciTech Connect

    L. V. Street

    2007-04-01

    The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility.

  18. Pollution prevention training for facility designers

    SciTech Connect

    Dorsey, J.A.; Raney, E.A.; Whitehead, J.K.

    1994-05-01

    An Orientation to Pollution Prevention for Facility Design training course was developed for the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Waste Minimization Division. The 3-hour course will be offered at the Hanford Quality Training and Resource Center beginning Summer, 1994. The course, intended for design engineers and project managers, contains two modules. The first module defines pollution prevention using actual success stories to illustrate pollution prevention concepts, benefits, and their relationship to design. The second module presents a newly developed job aid, the Pollution Prevention Design Guideline. The main challenges of developing the course were to present the material in a manner that participants would want to design for pollution prevention, and provide tools so that participants could design for pollution prevention. As such, the course is very interactive and uses a variety of presentation techniques. Participants are challenged to discuss the course materials in the context of their own design projects, and they practice using their new knowledge on an actual design project. The biggest measure of the course`s success is the extent to which the participants bring the materials back to their work place. An attitudinal survey and a knowledge-based questionnaire are administered before and after the course in order to gage this.

  19. Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment. Erratum

    SciTech Connect

    Smith, Gary L.

    2016-09-06

    This report refers to or contains Kg values for glasses LAWA44, LAWB45 and LAWC22 affected by calculations errors as identified by Papathanassiu et al. (2011). The corrected Kg values are reported in an erratum included in the revised version of the original report. The revised report can be referenced as follows: Pierce E. M. et al. (2004) Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment. PNNL-14805 Rev. 0 Erratum. Pacific Northwest National Laboratory, Richland, WA, USA.

  20. Engineering Evaluation/Cost Analysis for Power Burst Facility (PER-620) Final End State and PBF Vessel Disposal

    SciTech Connect

    B. C. Culp

    2007-05-01

    Preparation of this engineering evaluation/cost analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, (DOE and EPA 1995) which establishes the Comprehensive Environmental, Response, Compensation, and Liability Act non-time critical removal action process as an approach for decommissioning. The scope of this engineering evaluation/cost analysis is to evaluate alternatives and recommend a preferred alternative for the final end state of the PBF and the final disposal location for the PBF vessel.

  1. Conceptual design of the National Ignition Facility

    NASA Astrophysics Data System (ADS)

    Paisner, Jeffrey A.; Boyes, John D.; Kumpan, Steven A.; Lowdermilk, W. Howard; Sorem, Michael S.

    1995-12-01

    The Secretary of the U.S. Department of Energy (DOE) commissioned a conceptual design report (CDR) for the National Ignition Facility (NIF) in January 1993 as part of a key decision zero (KD0), justification of mission need. Motivated by the progress to date by the inertial confinement fusion (ICF) program in meeting the Nova technical contract goals established by the National Academy of Sciences in 1989, the Secretary requested a design using a solid-state laser driver operating at the third harmonic (0.35 micrometer) of neodymium (Nd) glass. The participating ICF laboratories signed a memorandum of agreement in August 1993, and established a project organization, including a technical team from the Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the Laboratory for Laser Energetics at the University of Rochester. Since then, we completed the NIF conceptual design, based on standard construction at a generic DOE defense program's site, and issued a 7,000-page, 27-volume CDR in May 1994. Over the course of the conceptual design study, several other key documents were generated, including a facilities requirements document, a conceptual design scope and plan, a target physics design document, a laser design cost basis document, a functional requirements document, an experimental plan for indirect drive ignition, and a preliminary hazards analysis (PHA) document. DOE used the PHA to categorize the NIF as a low-hazard, non-nuclear facility. On October 21, 1994 the Secretary of Energy issued a key decision one (KD1) for the NIF, which approved the project and authorized DOE to request Office of Management and Budget-approval for congressional line-item FY 1996 NIF funding for preliminary engineering design and for National Environmental Policy Act activities. In addition, the Secretary declared Livermore as the preferred site for constructing the NIF. In February 1995, the NIF Project was

  2. National Ignition Facility Target Design and Fabrication

    SciTech Connect

    Cook, R C; Kozioziemski, B J; Nikroo, A; Wilkens, H L; Bhandarkar, S; Forsman, A C; Haan, S W; Hoppe, M L; Huang, H; Mapoles, E; Moody, J D; Sater, J D; Seugling, R M; Stephens, R B; Takagi, M; Xu, H W

    2007-12-10

    The current capsule target design for the first ignition experiments at the NIF Facility beginning in 2009 will be a copper-doped beryllium capsule, roughly 2 mm in diameter with 160-{micro}m walls. The capsule will have a 75-{micro}m layer of solid DT on the inside surface, and the capsule will driven with x-rays generated from a gold/uranium cocktail hohlraum. The design specifications are extremely rigorous, particularly with respect to interfaces, which must be very smooth to inhibit Rayleigh-Taylor instability growth. This paper outlines the current design, and focuses on the challenges and advances in capsule fabrication and characterization; hohlraum fabrication, and D-T layering and characterization.

  3. ECONOMIC AND ENVIRONMENTAL ANALYSIS OF TECHNOLOGIES TO TREAT MERCURY AND DISPOSE IN A WASTE CONTAINMENT FACILITY

    EPA Science Inventory

    This report is intended to describe an economic and environmental analysis of a number of technologies for the treatment and disposal of elemental mercury. The analysis considers three treatment technologies that convert elemental mercury into a stable form of mercury. The techno...

  4. ECONOMIC AND ENVIRONMENTAL ANALYSIS OF TECHNOLOGIES TO TREAT MERCURY AND DISPOSE IN A WASTE CONTAINMENT FACILITY

    EPA Science Inventory

    This report is intended to describe an economic and environmental analysis of a number of technologies for the treatment and disposal of elemental mercury. The analysis considers three treatment technologies that convert elemental mercury into a stable form of mercury. The techno...

  5. Integrated safeguards and facility design and operations

    SciTech Connect

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by insiders requires careful communication and management of safeguards-relevant information on a timely basis. The separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification and careful attention to management of information can result in effective safeguards integration. Whether designing new systems or analyzing existing ones, understanding the interface between facility operations and safeguards is critical to cost-effective integrated safeguards systems that meet modern standards of performance.

  6. Accelerator Design Concept for Future Neutrino Facilities

    SciTech Connect

    ISS Accelerator Working Group; Zisman, Michael S; Berg, J. S.; Blondel, A.; Brooks, S.; Campagne, J.-E.; Caspar, D.; Cevata, C.; Chimenti, P.; Cobb, J.; Dracos, M.; Edgecock, R.; Efthymiopoulos, I.; Fabich, A.; Fernow, R.; Filthaut, F.; Gallardo, J.; Garoby, R.; Geer, S.; Gerigk, F.; Hanson, G.; Johnson, R.; Johnstone, C.; Kaplan, D.; Keil, E.; Kirk, H.; Klier, A.; Kurup, A.; Lettry, J.; Long, K.; Machida, S.; McDonald, K.; Meot, F.; Mori, Y.; Neuffer, D.; Palladino, V.; Palmer, R.; Paul, K.; Poklonskiy, A.; Popovic, M.; Prior, C.; Rees, G.; Rossi, C.; Rovelli, T.; Sandstrom, R.; Sevior, R.; Sievers, P.; Simos, N.; Torun, Y.; Vretenar, M.; Yoshimura, K.; Zisman, Michael S

    2008-02-03

    This document summarizes the findings of the Accelerator Working Group (AWG) of the International Scoping Study (ISS) of a Future Neutrino Factory and Superbeam Facility. The work of the group took place at three plenary meetings along with three workshops, and an oral summary report was presented at the NuFact06 workshop held at UC-Irvine in August, 2006. The goal was to reach consensus on a baseline design for a Neutrino Factory complex. One aspect of this endeavor was to examine critically the advantages and disadvantages of the various Neutrino Factory schemes that have been proposed in recent years.

  7. Lessons Learned From a Decade of Design, Construction, and Operations of the Environmental Management Waste Management Facility in Oak Ridge, Tennessee - 12062

    SciTech Connect

    Williams, Joe

    2012-07-01

    The Environmental Management Waste Management Facility (EMWMF) is the Department of Energy's on-site disposal facility for radioactive and hazardous waste generated by the CERCLA cleanup of the Oak Ridge Reservation (ORR). EMWMF recently completed building out to its maximum site capacity and is approaching a decade of operating experience. In meeting the challenges of design, construction, and operation of a mixed waste and low-level radioactive waste disposal facility within the framework of CERCLA, the Bechtel Jacobs Company LLC (BJC) project team learned valuable lessons that may be beneficial to other disposal facilities. Since project inception in 1998, the scope of the effort includes five regulator-approved designs, four phases of construction, and utilization of half of EMWMF's 1.63 M m{sup 3} of airspace during disposal of waste streams from across the ORR. Funding came from the broadest possible range of sources - privatization, American Recovery and Reinvestment Act, and two funding appropriation accounts. In the process of becoming the cost effective disposal outlet for the majority of the ORR cleanup waste, EMWMF overcame numerous challenges. Lessons learned were a key factor in achieving that success. Many of EMWMF's challenges are common to other disposal facilities. Sharing the successes and lessons learned will help other facilities optimize design, construction, and operations. (author)

  8. Grout disposal facility vault exhauster: Technical background document on demonstration of best available control technology for toxics

    SciTech Connect

    Glissmeyer, J.A.; Glantz, C.S.; Rittman, P.D.

    1994-09-01

    The Grout Disposal Facility (GDF) is currently operated on the US Department of Energy`s Hanford Site. The GDF is located near the east end of the Hanford Site`s 200 East operations area, and is used for the treatment and disposal of low-level radioactive liquid wastes. In the grout treatment process, selected radioactive wastes from double-shell tanks are mixed with grout-forming solids; the resulting grout slurry is pumped to near-surface concrete vaults for solidification and permanent disposal. As part of this treatment process, small amounts of toxic particles and volatile organic compounds (VOCs) may be released to the atmosphere through the GDF`s exhaust system. This analysis constitutes a Best Available Control Technology for Toxics (T-BACT) study, as required in the Washington Administrative Code (WAC 173-460) to support a Notice of Construction for the operation of the GDF exhaust system at a modified flow rate that exceeds the previously permitted value. This report accomplishes the following: assesses the potential emissions from the GDF; estimates air quality impacts to the public from toxic air pollutants; identifies control technologies that could reduce GDF emissions; evaluates impacts of the control technologies; and recommends appropriate emissions controls.

  9. Issues in the review of a license application for an above grade low-level radioactive waste disposal facility

    SciTech Connect

    Ringenberg, J.D.

    1993-03-01

    In December 1987, Nebraska was selected by the Central Interstate Compact (CIC) Commission as the host state for the construction of a low-level radioactive waste disposal facility. After spending a year in the site screening process, the Compact`s developer, US Ecology, selected three sites for detailed site characterization. These sites were located in Nemaha, Nuckolls and Boyd Counties. One year later the Boyd County site was selected as the preferred site and additional site characterization studies were undertaken. On July 29, 1990, US Ecology submitted a license application to the Nebraska Department of Environmental Control (now Department of Environmental Quality-NDEQ). This paper will present issues that the NDEQ has dealt with since Nebraska`s selection as the host state for the CIC facility.

  10. Features, events, processes, and safety factor analysis applied to a near-surface low-level radioactive waste disposal facility

    SciTech Connect

    Stephens, M.E.; Dolinar, G.M.; Lange, B.A.

    1995-12-31

    An analysis of features, events, processes (FEPs) and other safety factors was applied to AECL`s proposed IRUS (Intrusion Resistant Underground Structure) near-surface LLRW disposal facility. The FEP analysis process which had been developed for and applied to high-level and transuranic disposal concepts was adapted for application to a low-level facility for which significant efforts in developing a safety case had already been made. The starting point for this process was a series of meetings of the project team to identify and briefly describe FEPs or safety factors which they thought should be considered. At this early stage participants were specifically asked not to screen ideas. This initial list was supplemented by selecting FEPs documented in other programs and comments received from an initial regulatory review. The entire list was then sorted by topic and common issues were grouped, and issues were classified in three priority categories and assigned to individuals for resolution. In this paper, the issue identification and resolution process will be described, from the initial description of an issue to its resolution and inclusion in the various levels of the safety case documentation.

  11. Potential impacts of 40 CFR 193 on the development of low-level radioactive waste disposal facilities

    SciTech Connect

    Alvarado, R.A.

    1989-11-01

    Since the publication of the Advanced Notice of Proposed Rulemaking in August, 1983, the proposed environmental regulations regarding low-level radioactive waste have become a serious uncertainty in the development of new low-level radioactive waste disposal facilities. The proposed rule has been discussed on several occasions by the Technical Coordinating Committee and the purpose of this paper is to present the results of the Committee`s discussions regarding the proposed rule. The proposed standard has several closely related elements. The rule would prescribe limits on radiation exposure to individuals during processing, management and storage of low-level radioactive waste. It would set BRC levels and also set dose standards for the period following site closure. An important portion of the standard, as far as developing new facilities, is the ground water protection standard. The comments received during developing of 40 CFR 193 has also led the Environmental Protection Agency to propose 40 CFR 764 governing the disposal of naturally occurring radioactive material or NORM.

  12. Tazerka multiwell FPSU the design of production facilities

    SciTech Connect

    Rietveld, R.J.C.; Biss, N.C.; Gelderblom, D.

    1983-09-01

    This paper will review the problems and the solutions associated with the design of the production facilities on the Multiwell Floating-Production and Storage Unit (FPSU) operated by Shell Tunirex in the Tazerka field, offshore Tunisia, on behalf of a joint venture with AGIP (Africa) and Enterprise Tunisienne d'Activites Petrolieres. Economics and product specification dictated the application of special techniques in the production of, and utility of, designs as regards process flexibility, gas disposal, power generation and pollution prevention. The field, containing estimated reserves of 8-10 million barrels of recoverable oil, is located in deep water (140-300m). To be economic, a novel application of multi-well floating-production and storage concept was developed. It was desirable to use a single process train with as near a 100% on-stream factor as possible. While not the first application of a flow station on a weather-vaning unit, it is believed to be the first to process crude directly from several subsea wells.

  13. Radiological performance assessment for the E-Area Vaults Disposal Facility. Appendices A through M

    SciTech Connect

    Cook, J.R.

    1994-04-15

    These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file. (GHH)

  14. Confined Disposal Facility and Maintenance Dredging of the Les Cheneaux Island Federal Navigation Channels, Michigan.

    DTIC Science & Technology

    1979-01-01

    extends 15 miles eastward. The islands, their neighboring shoals, and the numerous points jutting among them from the irregular mainland coast, have a...available, such as beach nourishment or highway construction. Under current laws additional costs of such a disposal method , if any, would have to be borne...entrance, a middle entrance, and a west entrance. The east entrance extends from Penny Island up through Scammons Harbor and into Cedar- ville Bay along

  15. Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites

    SciTech Connect

    A. Jeff Sondrup; Annette L. Schafter

    2010-09-01

    Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratory’s proposed remote handled low-level waste disposal facility. 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 flood impacts are required to meet the Department of Energy’s Low-Level Waste requirements (DOE-O 435.1), its natural phenomena hazards assessment criteria (DOE-STD-1023-95), and the Radioactive Waste Management Manual (DOE M 435.1-1) guidance in addition to being required by the National Environmental Policy Act (NEPA) environmental assessment (EA). Potential sources of water evaluated include those arising from (1) local precipitation events, (2) precipitation events occurring off of the INL (off-site precipitation), and (3) increased flows in the Big Lost River in the event of a Mackay Dam failure. On-site precipitation events include potential snow-melt and rainfall. Extreme rainfall events were evaluated for the potential to create local erosion, particularly of the barrier placed over the disposal facility. Off-site precipitation carried onto the INL by the Big Lost River channel was evaluated for overland migration of water away from the river channel. Off-site precipitation sources evaluated were those occurring in the drainage basin above Mackay Reservoir. In the worst-case scenarios, precipitation occurring above Mackay Dam could exceed the dam’s capacity, leading to overtopping, and eventually complete dam failure. Mackay Dam could also fail during a seismic event or as a result of mechanical piping. Some of the water released during dam failure, and contributing precipitation, has the potential of being carried onto the INL in the Big Lost River channel. Resulting overland flows from these flood sources were evaluated for

  16. A conceptual subsurface facility design for a high-level nuclear waste repository at Yucca Mountain

    SciTech Connect

    McKenzie, D.G., III; Bhattacharyya, K.K.; Segrest, A.M.

    1996-09-01

    The US Department of Energy is responsible for the design, construction, operation and closure of a repository in which to permanently dispose of the nation`s high level nuclear waste. In addition to the objective of safely isolating the waste inventory, the repository must provide a safe working environment for its workforce, and protect the public. The conceptual design for this facility is currently being developed. Tunnel Boring Machine will be used to excavate 228 kilometers of tunneling to construct the facility over a 30 year period. The excavation operations will be physically separated from the waste emplacement operations, and each operation will have its own dedicated ventilation system. The facility is being designed to remain open for 150 years.

  17. 78 FR 77108 - Surplus Property Notice at a Military Installation Designated for Disposal: Pueblo Chemical Depot...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-20

    ... From the Federal Register Online via the Government Publishing Office ] DEPARTMENT OF DEFENSE Department of the Army Surplus Property Notice at a Military Installation Designated for Disposal: Pueblo Chemical Depot, Colorado AGENCY: Department of the Army, DoD. ACTION: Notice. SUMMARY: This notice provides...

  18. 76 FR 40345 - Information on Surplus Land at a Military Installation Designated for Disposal: Naval Station...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-08

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF DEFENSE Department of the Navy Information on Surplus Land at a Military Installation Designated for Disposal: Naval... satisfy military housing requirements in the Gulf Coast region. Notice of Surplus Property. Pursuant to...

  19. 75 FR 54497 - Ocean Dumping; Guam Ocean Dredged Material Disposal Site Designation

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-08

    ... at the site will be limited to a maximum of 1 million cubic yards (764,555 cubic meters) per calendar...). However, all dredged material must be discharged within a smaller 3,280 foot (1,000 meter) diameter...,790 feet (2,680 meters). D. Disposal Volume Limit G-DODS is designated for a maximum annual dredged...

  20. 46 CFR 162.050-15 - Designation of facilities.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... organization, equipment for conducting sample analysis, and the materials necessary to perform the tests; (2... facilities. (a) Each request for designation as a facility authorized to perform approval tests must be... following: (1) Name and address of the facility. (2) Each type of equipment the facility proposes to...

  1. 46 CFR 162.050-15 - Designation of facilities.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... organization, equipment for conducting sample analysis, and the materials necessary to perform the tests; (2... facilities. (a) Each request for designation as a facility authorized to perform approval tests must be... following: (1) Name and address of the facility. (2) Each type of equipment the facility proposes to...

  2. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    SciTech Connect

    Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

    2010-07-01

    The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

  3. ORNL results for Test Case 1 of the International Atomic Energy Agency`s research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

    SciTech Connect

    Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

    1993-07-01

    The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled ```The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.`` The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault.

  4. The thermal neutron facility HOTNES: theoretical design.

    PubMed

    Bedogni, R; Pietropaolo, A; Gomez-Ros, J M

    2017-09-01

    HOTNES (HOmogeneous Thermal NEutron Source) is a thermal neutron irradiation facility with extended and very uniform irradiation area. A (241)Am-B radionuclide neutron source with nominal strenght 3.5×10(6) s(-1) is located on bottom of a large cylindrical cavity (30cm diameter, 70cm in height) delimited by polyethylene walls. The upper part of this volume (30cm diameter, 40cm in height) is used to irradiate samples. A polyethylene cylinder, acting as shadowing object, prevents fast neutrons to directly reach the irradiation volume. Indeed neutrons can only reach the irradiation volume after multiple scattering with the cavity walls. The facility was designed trough extensive calculations with MCNPX. Irradiation planes are disks with 30cm diameter, centred on the cavity axis, and parallel to the cavity bottom. The value of thermal fluence in a given irradiation plane is as uniform as 1-2%. The value of thermal fluence rate simply depends on the height from the cavity bottom. Values of thermal fluence rate in the range 700-1000cm(-2)s(-1) are available, depending on the irradiation plane chosen. The fraction of thermal neutrons is in the order of 90%, also depending on the irradiation plane. The angular distribution of thermal neutrons is roughly isotropic. Taking advantage of the HOTNES design, even large devices can be uniformly irradiated. This work presents HOTNES's design and describes the neutron field in the irradiation volume in terms of spatial, energy and direction distributions. Copyright © 2017 Elsevier Ltd. All rights reserved.

  5. Pre-title I safety evaluation for the retrieval operations of transuranic waste drums in the Solid Waste Disposal Facility. Revision 2

    SciTech Connect

    Rabin, M.S.

    1992-08-01

    Phase I of the Transuranic (TRU) Waste Facility Line Item Project includes the retrieval and safe storage of the pad drums that are stored on TRU pads 2-6 in the Solid Waste Disposal Facility (SWDF). Drums containing TRU waste were placed on these pads as early as 1974. The pads, once filled, were mounded with soil. The retrieval activities will include the excavation of the soil, retrieval of the pad drums, placing the drums in overpacks (if necessary) and venting and purging the retrieved drums. Once the drums have been vented and purged, they will be transported to other pads within the SWDF or in a designated area until they are eventually treated as necessary for ultimate shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This safety evaluation provides a bounding assessment of the radiological risk involved with the drum retrieval activities to the maximally exposed offsite individual and the co-located worker. The results of the analysis indicate that the risk to the maximally exposed offsite individual and the co-located worker using maximum frequencies and maximum consequences are within the acceptance criteria defined in WSRC Procedural Manual 9Q. The purpose of this evaluation is to demonstrate the incremental risk from the SWDF due to the retrieval activities for use as design input only. As design information becomes available, this evaluation can be revised to satisfy the safety analysis requirements of DOE Orders 4700 and 5480.23.

  6. Ford Motor Company NDE facility shielding design.

    PubMed

    Metzger, Robert L; Van Riper, Kenneth A; Jones, Martin H

    2005-01-01

    Ford Motor Company proposed the construction of a large non-destructive evaluation laboratory for radiography of automotive power train components. The authors were commissioned to design the shielding and to survey the completed facility for compliance with radiation doses for occupationally and non-occupationally exposed personnel. The two X-ray sources are Varian Linatron 3000 accelerators operating at 9-11 MV. One performs computed tomography of automotive transmissions, while the other does real-time radiography of operating engines and transmissions. The shield thickness for the primary barrier and all secondary barriers were determined by point-kernel techniques. Point-kernel techniques did not work well for skyshine calculations and locations where multiple sources (e.g. tube head leakage and various scatter fields) impacted doses. Shielding for these areas was determined using transport calculations. A number of MCNP [Briesmeister, J. F. MCNPCA general Monte Carlo N-particle transport code version 4B. Los Alamos National Laboratory Manual (1997)] calculations focused on skyshine estimates and the office areas. Measurements on the operational facility confirmed the shielding calculations.

  7. Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1

    SciTech Connect

    Not Available

    1994-03-01

    This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

  8. 77 FR 63312 - Notice of Intent: Designation of an Ocean Dredged Material Disposal Site (ODMDS) in Eastern Long...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-16

    ... AGENCY Notice of Intent: Designation of an Ocean Dredged Material Disposal Site (ODMDS) in Eastern Long... potential designation of one or more Ocean Dredged Material Disposal Sites (ODMDS) to serve the eastern Long... Environmental Management; and Rhode Island Coastal Resources Management Council. SUPPLEMENTARY INFORMATION: The...

  9. Design of a fusion engineering test facility

    SciTech Connect

    Sager, P.H.

    1980-01-01

    The fusion Engineering Test Facility (ETF) is being designed to provide for engineering testing capability in a program leading to the demonstration of fusion as a viable energy option. It will combine power-reactor-type components and subsystems into an integrated tokamak system and provide a test bed to test blanket modules in a fusion environment. Because of the uncertainties in impurity control two basic designs are being developed: a design with a bundle divertor (Design 1) and one with a poloidal divertor (Design 2). The two designs are similar where possible, the latter having somewhat larger toroidal field (TF) coils to accommodate removal of the larger torus sectors required for the single-null poloidal divertor. Both designs have a major radius of 5.4 m, a minor radius of 1.3 m, and a D-shaped plasma with an elongation of 1.6. Ten TF coils are incorporated in both designs, producing a toroidal field of 5.5 T on-axis. The ohmic heating and equilibrium field (EF) coils supply sufficient volt-seconds to produce a flat-top burn of 100 s and a duty cycle of 135 s, including a start of 12 s, a burn termination of 10 s, and a pumpdown of 13 s. The total fusion power during burn is 750 MW, giving a neutron wall loading of 1.5 MW/m/sup 2/. In Design 1 of the poloidal field (PF) coils except the fast-response EF coils are located outside the FT coils and are superconducting. The fast-response coils are located inside the TF coil bore near the torus and are normal conducting so that they can be easily replaced.In Design 2 all of the PF coils are located outside the TF coils and are superconducting. Ignition is achieved with 60 MW of neutral beam injection at 150 keV. Five megawatts of radio frequency heating (electron cyclotron resonance heating) is used to assist in the startup and limit the breakdown requirement to 25 V.

  10. Designs for Learning: 55 Exemplary Educational Facilities. Education and Skills.

    ERIC Educational Resources Information Center

    Organisation for Economic Cooperation and Development, Paris (France). Programme on Educational Building.

    This document examines 55 educational facilities throughout the world whose quality designs were deemed instrumental in providing an environment for a quality educational process to emerge. Each entry provides facility statistics such as number of students, the facility's age and type, and name of the architectural firm responsible for its design.…

  11. Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

    SciTech Connect

    Cook, J.R.

    2001-02-20

    This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC.

  12. Issues in designing transport layer multicast facilities

    NASA Technical Reports Server (NTRS)

    Dempsey, Bert J.; Weaver, Alfred C.

    1990-01-01

    Multicasting denotes a facility in a communications system for providing efficient delivery from a message's source to some well-defined set of locations using a single logical address. While modem network hardware supports multidestination delivery, first generation Transport Layer protocols (e.g., the DoD Transmission Control Protocol (TCP) (15) and ISO TP-4 (41)) did not anticipate the changes over the past decade in underlying network hardware, transmission speeds, and communication patterns that have enabled and driven the interest in reliable multicast. Much recent research has focused on integrating the underlying hardware multicast capability with the reliable services of Transport Layer protocols. Here, we explore the communication issues surrounding the design of such a reliable multicast mechanism. Approaches and solutions from the literature are discussed, and four experimental Transport Layer protocols that incorporate reliable multicast are examined.

  13. EURO-CARES Sample Curation Facility: Preliminary Design

    NASA Astrophysics Data System (ADS)

    Hutzler, A.; Ferrière, L.; Bennett, A.; Brucato, J. R.; Debaille, V.; Folco, L.; Longobardo, A.; Meneghin, A.; Palomba, E.; Pottage, T.; Smith, C. L.; Euro-Cares Consortium

    2016-08-01

    EURO-CARES is a multinational project, funded under the European Commission's Horizon2020 research programme to create a roadmap of a European Extra-terrestrial Sample Curation Facility. We present here a preliminary design of the facility.

  14. Space power distribution system technology. Volume 3: Test facility design

    NASA Technical Reports Server (NTRS)

    Decker, D. K.; Cannady, M. D.; Cassinelli, J. E.; Farber, B. F.; Lurie, C.; Fleck, G. W.; Lepisto, J. W.; Messner, A.; Ritterman, P. F.

    1983-01-01

    The AMPS test facility is a major tool in the attainment of more economical space power. The ultimate goals of the test facility, its primary functional requirements and conceptual design, and the major equipment it contains are discussed.

  15. Hybrid and disposable facilities for manufacturing of biopharmaceuticals: pros and cons.

    PubMed

    Ravisé, Aline; Cameau, Emmanuelle; De Abreu, Georges; Pralong, Alain

    2009-01-01

    Modern biotechnology has grown over the last 35 years to a maturing industry producing and delivering high-value biopharmaceuticals that yield important medical and economical benefits. The constantly increasing need for biopharmaceuticals and significant costs related to time-consuming R&D work makes this industry risky and highly competitive. This trend is confirmed by the important number of biopharmaceuticals that are actually under development at all stages by all major pharmaceutical industry companies. A consequence of this evolution is an increasing need for development and manufacturing capacity. The build up of traditional - stainless steel - technology is complicated, time consuming and very expensive. The decision for such a major investment needs to be taken early in the development cycle of a promising drug to cope with future demands for clinical trials and product launch. Possibilities for the reduction of R&D and manufacturing costs are therefore of significant interest in order to be competitive.In this chapter, four case studies are presented which outline ways to reduce significantly R&D and manufacturing costs by using disposable technology in the frame of a the transfer of an antibody manufacturing process, the preparation of media and buffers in commercial manufacturing and a direct comparison of a traditional and a fully disposable pilot plant.

  16. Reference design and operations for deep borehole disposal of high-level radioactive waste.

    SciTech Connect

    Herrick, Courtney Grant; Brady, Patrick Vane; Pye, Steven; Arnold, Bill Walter; Finger, John Travis; Bauer, Stephen J.

    2011-10-01

    A reference design and operational procedures for the disposal of high-level radioactive waste in deep boreholes have been developed and documented. The design and operations are feasible with currently available technology and meet existing safety and anticipated regulatory requirements. Objectives of the reference design include providing a baseline for more detailed technical analyses of system performance and serving as a basis for comparing design alternatives. Numerous factors suggest that deep borehole disposal of high-level radioactive waste is inherently safe. Several lines of evidence indicate that groundwater at depths of several kilometers in continental crystalline basement rocks has long residence times and low velocity. High salinity fluids have limited potential for vertical flow because of density stratification and prevent colloidal transport of radionuclides. Geochemically reducing conditions in the deep subsurface limit the solubility and enhance the retardation of key radionuclides. A non-technical advantage that the deep borehole concept may offer over a repository concept is that of facilitating incremental construction and loading at multiple perhaps regional locations. The disposal borehole would be drilled to a depth of 5,000 m using a telescoping design and would be logged and tested prior to waste emplacement. Waste canisters would be constructed of carbon steel, sealed by welds, and connected into canister strings with high-strength connections. Waste canister strings of about 200 m length would be emplaced in the lower 2,000 m of the fully cased borehole and be separated by bridge and cement plugs. Sealing of the upper part of the borehole would be done with a series of compacted bentonite seals, cement plugs, cement seals, cement plus crushed rock backfill, and bridge plugs. Elements of the reference design meet technical requirements defined in the study. Testing and operational safety assurance requirements are also defined. Overall

  17. A sensitivity analysis of hazardous waste disposal site climatic and soil design parameters using HELP3

    SciTech Connect

    Adelman, D.D.; Stansbury, J.

    1997-12-31

    The Resource Conservation and Recovery Act (RCRA) Subtitle C, Comprehensive Environmental Response, Compensation, And Liability Act (CERCLA), and subsequent amendments have formed a comprehensive framework to deal with hazardous wastes on the national level. Key to this waste management is guidance on design (e.g., cover and bottom leachate control systems) of hazardous waste landfills. The objective of this research was to investigate the sensitivity of leachate volume at hazardous waste disposal sites to climatic, soil cover, and vegetative cover (Leaf Area Index) conditions. The computer model HELP3 which has the capability to simulate double bottom liner systems as called for in hazardous waste disposal sites was used in the analysis. HELP3 was used to model 54 combinations of climatic conditions, disposal site soil surface curve numbers, and leaf area index values to investigate how sensitive disposal site leachate volume was to these three variables. Results showed that leachate volume from the bottom double liner system was not sensitive to these parameters. However, the cover liner system leachate volume was quite sensitive to climatic conditions and less sensitive to Leaf Area Index and curve number values. Since humid locations had considerably more cover liner system leachate volume than and locations, different design standards may be appropriate for humid conditions than for and conditions.

  18. RESULTS FOR THE MAY 19, 2010 INADVERTENT TRANSFER TO THE SALTSTONE DISPOSAL FACILITY SLURRY: SAMPLE ANALYTICAL RESULTS

    SciTech Connect

    Reigel, M.; Cozzi, A.

    2010-08-17

    This report details the chemical analysis results for the characterization of the May 19, 2010 inadvertent transfer from the Saltstone Production Facility (SPF) to the Saltstone Disposal Facility (SDF). On May 19, 2010, the Saltstone Processing Facility (SPF) inadvertently transferred approximately 1800 gallons of untreated low-level salt solution from the salt feed tank (SFT) to Cell F of Vault 4. The transfer was identified and during safe configuration shutdown, approximately 70 gallons of SFT material was left in the Saltstone hopper. After the shutdown, the material in the hopper was undisturbed, while the SFT has received approximately 1400 gallons of drain water from the Vault 4 bleed system. The drain water path from Vault 4 to the SFT does not include the hopper (Figure 1); therefore it was determined that the material remaining in the hopper was the most representative sample of the salt solution transferred to the vault. To complete item No.5 of Reference 1, Savannah River National Laboratory (SRNL) was asked to analyze the liquid sample retrieved from the hopper for pH, and metals identified by the Resource Conservation and Recovery Act (RCRA). SRNL prepared a report to complete item No.5 and determine the hazardous nature of the transfer. Waste Solidification Engineering then instructed SRNL to provide a more detailed analysis of the slurried sample to assist in the determination of the portion of Tank 50 waste in the hopper sample.

  19. Assessment of Geochemical Environment for the Proposed INL Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect

    D. Craig Cooper

    2011-11-01

    Conservative sorption parameters have been estimated for the proposed Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility. This analysis considers the influence of soils, concrete, and steel components on water chemistry and the influence of water chemistry on the relative partitioning of radionuclides over the life of the facility. A set of estimated conservative distribution coefficients for the primary media encountered by transported radionuclides has been recommended. These media include the vault system, concrete-sand-gravel mix, alluvium, and sedimentary interbeds. This analysis was prepared to support the performance assessment required by U.S. Department of Energy Order 435.1, 'Radioactive Waste Management.' The estimated distribution coefficients are provided to support release and transport calculations of radionuclides from the waste form through the vadose zone. A range of sorption parameters are provided for each key transport media, with recommended values being conservative. The range of uncertainty has been bounded through an assessment of most-likely-minimum and most-likely-maximum distribution coefficient values. The range allows for adequate assessment of mean facility performance while providing the basis for uncertainty analysis.

  20. Disposal of radioactive waste

    NASA Astrophysics Data System (ADS)

    Van Dorp, Frits; Grogan, Helen; McCombie, Charles

    The aim of radioactive and non-radioactive waste management is to protect man and the environment from unacceptable risks. Protection criteria for both should therefore be based on similar considerations. From overall protection criteria, performance criteria for subsystems in waste management can be derived, for example for waste disposal. International developments in this field are summarized. A brief overview of radioactive waste sorts and disposal concepts is given. Currently being implemented are trench disposal and engineered near-surface facilities for low-level wastes. For low-and intermediate-level waste underground facilities are under construction. For high-level waste site selection and investigation is being carried out in several countries. In all countries with nuclear programmes, the predicted performance of waste disposal systems is being assessed in scenario and consequence analyses. The influences of variability and uncertainty of parameter values are increasingly being treated by probabilistic methods. Results of selected performance assessments show that radioactive waste disposal sites can be found and suitable repositories can be designed so that defined radioprotection limits are not exceeded.

  1. Ocean Disposal Site Monitoring

    EPA Pesticide Factsheets

    EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

  2. An exposure assessment of radionuclide emissions associated with potential mixed-low level waste disposal facilities at fifteen DOE sites

    SciTech Connect

    Lombardi, D.A.; Socolof, M.L.

    1996-05-01

    A screening method was developed to compare the doses received via the atmospheric pathway at 15 potential DOE MLLW (mixed low-level waste) sites. Permissible waste concentrations were back calculated using the radioactivity NESHAP (National Emissions Standards for Hazardous Air Pollutants) in 40 FR 61 (DOE Order 5820.2A performance objective). Site-specific soil and meteorological data were used to determine permissible waste concentrations (PORK). For a particular radionuclide, perks for each site do not vary by more than one order of magnitude. perks of {sup 14}C are about six orders of magnitude more restrictive than perks of {sup 3}H because of differences in liquid/vapor partitioning, decay, and exposure dose. When comparing results from the atmospheric pathway to the water and intruder pathways, {sup 14}C disposal concentrations were limited by the atmospheric pathway for most arid sites; for {sup 3}H, the atmospheric pathway was not limiting at any of the sites. Results of this performance evaluation process are to be used for planning for siting of disposal facilities.

  3. Incremental Risks of Transporting NARM to the LLW Disposal Facility at Hanford

    SciTech Connect

    Weiner, R.F.

    1999-02-23

    This study models the incremental radiological risk of transporting NARM to the Hanford commercial LLW facility, both for incident-free transportation and for possible transportation accidents, compared with the radiological risk of transporting LLW to that facility. Transportation routes are modeled using HIGHWAY 3.1 and risks are modeled using RADTRAN 4. Both annual population doses and risks, and annual average individual doses and risks are reported. Three routes to the Hanford site were modeled from Albany, OR, from Coeur d'Alene, ID (called the Spokane route), and from Seattle, WA. Conservative estimates are used in the RADTRAN inputs, and RADTRAN itself is conservative.

  4. Project W-441, cold vacuum drying facility design requirements document

    SciTech Connect

    O`Neill, C.T.

    1997-05-08

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage.

  5. Modern tornado design of nuclear and other potentially hazardous facilities

    SciTech Connect

    Stevenson, J.D.; Zhao, Y.

    1996-01-01

    Tornado wind loads and other tornado phenomena, including tornado missiles and differential pressure effects, have not usually been considered in the design of conventional industrial, commercial, or residential facilities in the United States; however, tornado resistance has often become a design requirement for certain hazardous facilities, such as large nuclear power plants and nuclear materials and waste storage facilities, as well as large liquefied natural gas storage facilities. This article provides a review of current procedures for the design of hazardous industrial facilities to resist tornado effects. 23 refs., 19 figs., 13 tabs.

  6. Calculation of absorbed dose around a facility for disposing of low activity natural radioactive waste (C3-dump).

    PubMed

    Jansen, J T M; Zoetelief, J

    2005-01-01

    A C3-dump is a facility for disposing of low activity natural radioactive waste containing the uranium series 238U, the thorium series 232Th and 40K. Only the external radiation owing to gamma rays, X-rays and annihilation photons is considered in this study. For two situations--the semi-infinite slab and the tourist geometry--the conversion coefficients from specific activity to air kerma rate at 1 m above the relevant level are calculated. In the first situation the waste material is in contact with the air but in the tourist geometry it is covered with a 1.35 m thick layer. For the calculations, the Monte Carlo radiation transport code MCNP is used. The yield and photon energy for each radionuclide are according to the database of Oak Ridge National Laboratory. For the tourist situation, the depth-dose distribution through the covering layer is calculated and extrapolated to determine the exit dose.

  7. Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling

    SciTech Connect

    Phifer, Mark A.; Smith, Frank G. III

    2013-06-21

    A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

  8. Saltstone Disposal Facility Mechanically Stabilized Earth Vault Closure Cap Degradation Base Case: Institutional Control To Pine Forest Scenario

    SciTech Connect

    Phifer, MA

    2004-03-19

    As part of the current Saltstone Disposal Facility (SDF) Performance Assessment (PA) revision, the closure cap configuration was reevaluated and closure cap degradation mechanisms and their impact upon infiltration through the closure cap was evaluated for the existing SDF concrete vaults (i.e. vaults 1 and 4) for the base case land use scenario (i.e. institutional control to pine forest scenario) and documented in Phifer and Nelson (2003). The closure cap configuration was modified from a compacted kaolin barrier layer concept to a geosynthetic clay layer (GCL) barrier layer concept. The degradation mechanisms developed included pine forest succession, erosion, and colloidal clay migration. These degradation mechanisms resulted in changes in the hydraulic properties of the closure cap layers and resulting increases in infiltration through the closure cap over time.

  9. Summary of treatment, storage, and disposal facility usage data collected from U.S. Department of Energy sites

    SciTech Connect

    Jacobs, A.; Oswald, K.; Trump, C.

    1995-04-01

    This report presents an analysis for the US Department of Energy (DOE) to determine the level and extent of treatment, storage, and disposal facility (TSDF) assessment duplication. Commercial TSDFs are used as an integral part of the hazardous waste management process for those DOE sites that generate hazardous waste. Data regarding the DOE sites` usage have been extracted from three sets of data and analyzed in this report. The data are presented both qualitatively and quantitatively, as appropriate. This information provides the basis for further analysis of assessment duplication to be documented in issue papers as appropriate. Once the issues have been identified and adequately defined, corrective measures will be proposed and subsequently implemented.

  10. Evaluation of a performance assessment methodology for low-level radioactive waste disposal facilities: Validation needs. Volume 2

    SciTech Connect

    Kozak, M.W.; Olague, N.E.

    1995-02-01

    In this report, concepts on how validation fits into the scheme of developing confidence in performance assessments are introduced. A general framework for validation and confidence building in regulatory decision making is provided. It is found that traditional validation studies have a very limited role in developing site-specific confidence in performance assessments. Indeed, validation studies are shown to have a role only in the context that their results can narrow the scope of initial investigations that should be considered in a performance assessment. In addition, validation needs for performance assessment of low-level waste disposal facilities are discussed, and potential approaches to address those needs are suggested. These areas of topical research are ranked in order of importance based on relevance to a performance assessment and likelihood of success.

  11. Assessing risks to fish populations near a proposed disposal facility for used nuclear fuel

    SciTech Connect

    Hart, D.; Miesenheimer, P.; Hull, R.

    1995-12-31

    The concept of used nuclear fuel disposal in the Canadian Shield is currently undergoing a federal environmental assessment review process. As part of this review, potential risks to brook trout populations in the vicinity of such an underground repository were considered. Chemical fate, transport and exposure models have been utilized to estimate the dose rates from released radionuclides and other fuel constituents, and these likely will not be sufficient to harm fish in nearby streams. However, other stressors such as habitat alteration (e.g., loss of upwelling) and/or fishing pressure associated with increased public access could have significant population impacts if the site is located in a pristine northern region. Population models are utilized to explore the risks of local population reduction for different combinations of fishing pressure and habitat degradation.

  12. DARHT : integration of shielding design and analysis with facility design /

    SciTech Connect

    Boudrie, R. L.; Brown, T. H.; Gilmore, W. E.; Downing, J. N. , Jr.; Hack, Alan; McClure, D. A.; Nelson, C. A.; Wadlinger, E. Alan; Zumbro, M. V.

    2002-01-01

    The design of the interior portions of the Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility incorporated shielding and controls from the beginning of the installation of the Accelerators. The purpose of the design and analysis was to demonstrate the adequacy of shielding or to determine the need for additional shielding or controls. Two classes of events were considered: (1) routine operation defined as the annual production of 10,000 2000-ns pulses of electrons at a nominal energy of 20 MeV, some of which are converted to the x-ray imaging beam consisting of four nominal 60-ns pulses over the 2000-ns time frame, and (2) accident case defined as up to 100 2000-ns pulses of electrons accidentally impinging on some metallic surface, thereby producing x rays. Several locations for both classes of events were considered inside and outside of the accelerator hall buildings. The analysis method consisted of the definition of a source term for each case studied and the definition of a model of the shielding and equipment present between the source and the dose areas. A minimal model of the fixed existing or proposed shielding and equipment structures was used for a first approximation. If the resulting dose from the first approximation was below the design goal (1 rem/yr for routine operations, 5 rem for accident cases), then no further investigations were performed. If the result of the first approximation was above our design goals, the model was refined to include existing or proposed shielding and equipment. In some cases existing shielding and equipment were adequate to meet our goals and in some cases additional shielding was added or administrative controls were imposed to protect the workers. It is expected that the radiation shielding design, exclusion area designations, and access control features, will result in low doses to personnel at the DARHT Facility.

  13. Bomb chlorine-36 analysis in the characterization of unsaturated flow at a proposed radioactive waste disposal facility, Chihuahuan Desert, Texas

    NASA Astrophysics Data System (ADS)

    Scanlon, B. R.; Kubik, P. W.; Sharma, P.; Richter, B. C.; Gove, H. E.

    1990-12-01

    The distribution of anthropogenic chlorine-36 in the unsaturated zone is used to estimate the moisture flux at a study site in the Chihuahuan Desert, Texas, for a potential low-level radioactive waste disposal facility. The unsaturated zone at the study site is approximately 150 m thick; the uppermost section consists of 15 m of coarse-grained sediment that overlies 140 m of clay. The {36Cl}/{Cl} depth profile includes a well-defined peak ratio of 6.6×10 -12 at a depth of 0.5 m. A background {36Cl}/{Cl} ratio of 0.46 × 10 -12 below a depth of 1.25 m agrees with the predicted natural fallout of 0.50×10 -12 for this latitude. The measured total inventory of bomb 36Cl is 2.5 × 10 -12 atoms m -2, which is 73% of the predicted fallout at this latitude. The specific moisture flux based on the {36Cl}/{Cl} peak depth is 1.4 mm a -1, or 0.5% of the mean annual precipitation rate in the region. Because the bomb pulse is restricted to the root zone, it is not possible to determine if this infiltrating water will recharge the deep water table. The movement of liquid and vapor phases of water in the shallow, unsaturated zone is complex and includes both downward- and upward-directed flux components controlled by infiltration and evapotranspiration; therefore, Cl data that delineate the net movement of water over a long time period are critical in evaluation of the potential for radionuchde transport from disposal facilities.

  14. Reversing nuclear opposition: evolving public acceptance of a permanent nuclear waste disposal facility.

    PubMed

    Jenkins-Smith, Hank C; Silva, Carol L; Nowlin, Matthew C; deLozier, Grant

    2011-04-01

    Nuclear facilities have long been seen as the top of the list of locally unwanted land uses (LULUs), with nuclear waste repositories generating the greatest opposition. Focusing on the case of the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, we test competing hypotheses concerning the sources of opposition and support for siting the facility, including demographics, proximity, political ideology, and partisanship, and the unfolding policy process over time. This study tracks the changes of risk perception and acceptance of WIPP over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning an 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those whose residences are closest to the WIPP facility. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval, and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to gaining public acceptance, the most significant being the opening of the WIPP facility itself.

  15. Learning Design at White Sands Test Facility

    NASA Technical Reports Server (NTRS)

    Grotewiel, Shane

    2010-01-01

    During the Fall of 2010, I spent my time at NASA White Sands Test Facility in Las Cruces, NM as an Undergraduate Student Research Program (USRP) Intern. During that time, I was given three projects to work on: Large Altitude Simulation System (LASS) basket strainer, log books, and the design of a case for touch screen monitors used for simulations. I spent most of my time on the LASS basket strainer. The LASS system has a water feed line with a basket strainer that filters out rust. In 2009, there were three misfires which cost approximately $27,000 and about 8% of the allotted time. The strainer was getting a large change in pressure that would result in a shutdown of the system. I have designed a new basket that will eliminate the large pressure change and it can be used with the old basket strainer housing. The LASS system has three steam generators (modules). Documents pertaining to these modules are stored electronically, and the majority of the documents are not able to be searched with keywords, so they have to be gone through one by one. I have come up with an idea on how to organize these files so that the Propulsion Department may efficiently search through the documents needed. Propulsion also has a LASS simulator that incorporates two touch screen monitors. Currently these monitors are in six foot by two foot metal cabinet on wheels. During simulation these monitors are used in the block house and need to be taken out of the block house when not in use. I have designed different options for hand held cases for storing and transporting the monitors in and out of the block house. The three projects previously mentioned demonstrate my contributions to the Propulsion Department and have taught me real world experience that is essential in becoming a productive engineer.

  16. Performance and safety assessment of the co-location of the near surface radioactive waste disposal facilities and borehole disposal concept in the Philippines

    SciTech Connect

    Vargas, Edmundo; Reyes, Rolando; Palattao, Maria Visitacion; Nohay, Carl; Singayan, Alfonso; Aurelio, Mario; Gedeon, Matej; Luna, Roy Anthony C.

    2013-07-01

    The Philippine Nuclear Research Institute (PNRI) in collaboration with the interagency technical committee on radioactive waste has been undertaking a national project to find a final solution to the country's low to intermediate level radioactive waste. The strategy adopted was to co-locate 2 disposal concepts that will address the types of radioactive waste generated from the use of radioactive materials. This strategy is expected to compensate for the small volumes of waste generated in the Philippines as compared to countries with big nuclear energy programs. It will also take advantage of the benefits of a shared infrastructure and R and D work that accompany such project. The preferred site selected from previous site selection and investigations is underlain by highly fractured 'andesitic volcaniclastics' mantled by residual clayey soil which act as the aquifer or water bearing layer. Results of investigation show that the groundwater in the area is relatively dilute and acidic. Springs at the lower elevations of the footprint also indicate acidic waters. The relatively acidic water is attributed to the formation of sulfuric acid by the oxidation of the pyrite in the andesite. A preliminary post closure safety assessment was carried out using the GMS MODFLOW and HYDRUS softwares purchased through the International Atomic Energy Agency (IAEA) technical assistance. Results from MODFLOW modeling show that the radionuclide transport follows the natural gradient from the top of the hill down to the natural discharge zones. The vault dispersion model shows a circular direction from the vaults towards the faults and eventually to the creeks. The contaminant transport from borehole shows at least one confined plume from the borehole towards the creek designated as Repo1 and eventually follows downstream. The influx of surface water and rainfall to the disposal vault was modeled using the HYDRUS software. The pressure head and water content at the base of the

  17. Design and Operating Criteria for Fluorine Disposal by Reaction with Charcoal

    NASA Technical Reports Server (NTRS)

    Schmidt, Harold W.

    1959-01-01

    Experiments with the charcoal-fluorine reaction for the disposal of fluorine have shown generally that this method is effective over a wide range of conditions. Pure fluorine or fluorine diluted with nitrogen to concentrations as low as 0.3 percent fluorine may be disposed of efficiently within the rate limitation. Maximum feed rates have been established and are inversely proportional to the charcoal-bed particle diameter. Moisture content in the charcoal had no appreciable effect on the disposal efficiency after the reaction zone was established and the moisture was driven off by the heat of reaction. There was no evidence of bed poisoning resulting from continued use. Design parameters may be based on the stoichiometric requirements plus sufficient excess charcoal to maintain desired efficiency toward the end of a disposal operation. The length of time a given reactor may be used continuously is limited by the rate of fluorine input and the resistance of the system to heat and fluorine attack. Refractory-lined reactors have been in routine field use at the Lewis Research Center for over a year and have given satisfactory service over a wide range of conditions.

  18. 40 CFR 60.32c - Designated facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) program approval, even if the design capacity report is submitted earlier. (d) When a MSW landfill subject... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the guidelines apply is each existing MSW landfill for which construction, reconstruction or modification...

  19. 40 CFR 60.32c - Designated facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) program approval, even if the design capacity report is submitted earlier. (d) When a MSW landfill subject... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the guidelines apply is each existing MSW landfill for which construction, reconstruction or modification...

  20. 40 CFR 60.32c - Designated facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) program approval, even if the design capacity report is submitted earlier. (d) When a MSW landfill subject... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the guidelines apply is each existing MSW landfill for which construction, reconstruction or modification...

  1. 40 CFR 60.32c - Designated facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) program approval, even if the design capacity report is submitted earlier. (d) When a MSW landfill subject... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the guidelines apply is each existing MSW landfill for which construction, reconstruction or modification...

  2. 40 CFR 60.32c - Designated facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) program approval, even if the design capacity report is submitted earlier. (d) When a MSW landfill subject... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the guidelines apply is each existing MSW landfill for which construction, reconstruction or modification...

  3. Final closure cover for a Hanford radioactive mixed waste disposal facility

    SciTech Connect

    Johnson, K.D.

    1996-02-06

    This study provides a preliminary design for a RCRA mixed waste landfill final closure cover. The cover design was developed by a senior class design team from Seattle University. The design incorporates a layered design of indigenous soils and geosynthetics in a layered system to meet final closure cover requirements for a landfill as imposed by the Washington Administrative Code WAC-173-303 implementation of the Resource Conservation and Recovery Act.

  4. Criteria for the management of disposal sites for ocean dumping extension of interim designations

    SciTech Connect

    Not Available

    1980-01-16

    The US Environmental Protection Agency has promulgated amendments to its regulations on ocean dumping which extend the interim designation of certain ocean dumping sites pending completion of Environmental Impact Statements (EIS) and formal rulemaking procedures. Other sites, mainly those for dredged material disposal, will be extended pending completion of site designation studies and formal designation. The schedule for availability of draft EIS on 25 dumping sites and extension dates for the affected interim sites are discussed. This rule is effective as of 1/16/80. Comments must be received by 2/15/80.

  5. Estimate of Gaseous 14Carbon Concentrations Emanating from the Intermediate-Level Vault Disposal Facility

    SciTech Connect

    Kaplan, D

    2005-08-31

    {sup 14}Carbon-bearing resin waste will be disposed in the Low-Activity Waste (LAW) Intermediate Level Vaults (ILV) located in E-Area on the Savannah River Site (SRS). This waste will be buried in a cementitious environment in the vadose zone, i.e., the subsurface zone above the aquifer. As the resin ages, and equilibrates with slowly infiltrating water, it is expected that the {sup 14}C will partition to the solid, liquid, and gaseous phases. The objective of this task was to estimate the concentration of gaseous {sup 14}C in the waste pore space that is in contact with the resin leachate. The approach used to estimate this value was built largely around data generated from lysimeter studies that were conducted for 9 years. These lysimeters contained the same type of used resins (mixed-bed deionizer resins used in the purification of the heavy water moderator of SRS reactors) as are being disposed in the ILV. During the 9 year period, pore water {sup 14}C leaching concentrations were monitored to provide an excellent estimate of the long-term behavior of {sup 14}C release rates from the resins. Thermodynamic calculations were conducted to calculate {sup 14}CO{sub 2(g)} concentrations. These calculations included the {sup 14}C pore water data from the lysimeter study, and data from a field study that was a natural analogue to a long-term cementitious environment (Khoury et al. 1992). The calculations predicted an extremely low {sup 14}CO{sub 2(g)} concentration of 1.9 x 10{sup -7} Ci/m{sup 3} {sup 14}CO{sub 2(g)} in the air spaces above the resin leachate. This low concentrations is not surprising in light of both laboratory and field observations that concrete acts as a strong sorbent of CO{sub 2(g)}. This calculated {sup 14}CO{sub 2(g)} concentration will now be included in future risk calculations.

  6. Facility Design and Management: Innovative Approaches to Instruction.

    ERIC Educational Resources Information Center

    Goldfine, Bernard D.; Walker, M.

    Sport facility design and management courses rely heavily or exclusively upon lectures and readings--modes of instruction that engage students in a passive form of learning. This paper advocates one method of stimulating higher-level thinking and active learning in facility courses--the use of cooperative small-group learning. In facility courses,…

  7. Facility Flexibility and the Standardization of Building Design Modules.

    DTIC Science & Technology

    1982-09-01

    Entered) UNCLASSIFIED *C UNUTY CLASIFICATION OF THIS PAGII(Itm DOS eM I. Reviewed Army facility design standardization procedures, policies, and...standard modules around on facility flexibility in mind . Thus, decisions about a a computer screen, and give degrees of common fit facility’s functional

  8. Reduced scale National Ignition Facility capsule design

    NASA Astrophysics Data System (ADS)

    Dittrich, T. R.; Haan, S. W.; Marinak, M. M.; Pollaine, S. M.; McEachern, R.

    1998-10-01

    In this article we describe the design and simulated performance characteristics of an indirectly-driven inertial confinement fusion capsule which utilizes only 900 kJ of laser energy and 250 TW of laser power from the National Ignition Facility (NIF) [Paisner et al., Laser Focus World 30, 75 (1994)]. This intentional reduction in laser performance from the nominal NIF specifications of 1.8 MJ and 500 TW results in lowering the hohlraum x-ray drive temperature from 300 eV to 250 eV. These energy and radiation temperature reductions are believed to define a "lower bound" on the successful implosion of an ignition capsule. This reduced scale capsule has a beryllium ablator containing a radially varying copper dopant, and a cryogenic solid deuterium-tritium fuel layer surrounding a cavity filled with equilibrium vapor pressure gaseous deuterium and tritium. Two-dimensional simulations predict ignition and propagated burn from this capsule when either Rayleigh-Taylor instability or time-dependent drive asymmetry effects are included.

  9. Coping with a community stressor: a proposed hazardous waste disposal facility

    SciTech Connect

    Bachrach, K.M.

    1983-01-01

    This study examined a number of factors believed to influence community involvement. Residents of a rural community near Phoenix, Arizona, where a hazardous waste facility had been proposed to built, were interviewed at home in August 1982. Most residents were chosen at random (n = 70) while a smaller number (n = 29) were selected because of known involvement in activities regarding the hazardous waste facility. Residents who perceived the facility as a threat to their health, safety, and general well-being employed a number of coping strategies. Strategies to change or alter the source of stress, problem-focused coping, were associated with greater community involvement. Strategies to regulate one's emotional response to stress, emotion-focused coping, were associated with less community involvement. Increased self-efficacy and sense of community led to increased community involvement. Both measures indirectly influenced community involvement through different modes of coping. Self-efficacy was negatively related to emotion-focused coping while sense of community was positively related to problem-focused coping. Increased demoralization was associated with decreased self-efficacy, increased emotion-focused coping, and decreased community involvement. The results suggest that the psychologically most fragile residents are underrepresented in community activities, and that the use of high levels of emotion-focused coping may have been maladaptive.

  10. Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

    SciTech Connect

    Ranek, N.L.; Coalgate, J.L.

    1995-07-01

    The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process.

  11. A facile disposal of Bayer red mud based on selective flocculation desliming with organic humics.

    PubMed

    Huang, Yanfang; Han, Guihong; Liu, Jiongtian; Wang, Wenjuan

    2016-01-15

    Humics flocculant was applied in the disposal of Bayer red mud based on selective flocculation desliming process. The parameters affecting selective flocculation behavior such as flocculant dosage, slurry pH and agitation intensity were studied. For flocculating mechanism analysis, the iron mineral and the flocs product were characterized by ζ-potential testing, settling experiments, optical microscope and SEM imaging. The results show that humics exhibits a good selective flocculation performance in the high alkaline pH range. With an optimal condition of 2% solid density, flocculant dosage 30 mg L(-1), Na2SiO3 dosage 200 mg L(-1), slurry pH 10.0 and agitation speed 1000 rpm, the recovery of iron minerals of 86.25±1.31%, the iron grade of concentrate of 61.12±0.10%, the separation index of 0.69±0.02 can be obtained in the selective flocculation. It is found that the adsorption bridging of humics polymer dominates the selectively flocculating the iron minerals. Large flocs or aggregates with a better settling capacity are generated because of humics occurring. The maximum settling velocity of 38.23±1.51 m h(-1) is reached at pH 10. This work brings the easiness in directly recovering fine particle size of iron-bearing minerals from red mud.

  12. Fate of steroid hormones and endocrine activities in swine manure disposal and treatment facilities.

    PubMed

    Combalbert, Sarah; Bellet, Virginie; Dabert, Patrick; Bernet, Nicolas; Balaguer, Patrick; Hernandez-Raquet, Guillermina

    2012-03-01

    Manure may contain high concern endocrine-disrupting compounds (EDCs) such as steroid hormones, naturally produced by pigs, which are present at μgL(-1) levels. Manure may also contain other EDCs such as nonylphenols (NP), polycyclic aromatic hydrocarbons (PAHs) and dioxins. Thus, once manure is applied to the land as soil fertilizer these compounds may reach aquifers and consequently living organisms, inducing abnormal endocrine responses. In France, manure is generally stored in anaerobic tanks prior spreading on land; when nitrogen removal is requested, manure is treated by aerobic processes before spreading. However, little is known about the fate of hormones and multiple endocrine-disrupting activities in such manure disposal and treatment systems. Here, we determined the fate of hormones and diverse endocrine activities during manure storage and treatment by combining chemical analysis and in vitro quantification of estrogen (ER), aryl hydrocarbon (AhR), androgen (AR), pregnane-X (PXR) and peroxysome proliferator-activated γ (PPARγ) receptor-mediated activities. Our results show that manure contains large quantities of hormones and activates ER and AhR, two of the nuclear receptors studied. Most of these endocrine activities were found in the solid fraction of manure and appeared to be induced mainly by hormones and other unidentified pollutants. Hormones, ER and AhR activities found in manure were poorly removed during manure storage but were efficiently removed by aerobic treatment of manure. Copyright © 2011 Elsevier Ltd. All rights reserved.

  13. Waste Form Release Calculations for the 2005 Integrated Disposal Facility Performance Assessment

    SciTech Connect

    Bacon, Diana H.; McGrail, B PETER.

    2005-07-26

    A set of reactive chemical transport calculations was conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal system located on the Hanford Site. Two-dimensional simulations were run until the waste form release rates reached a quasi-stationary-state, usually after 2,000 to 4,000 yr. The primary difference between the waste form release simulations for the 2001 ILAW PA, and the simulations described herein, is the number of different materials considered. Whereas the previous PA considered only LAWABP1 glass, the current PA also describes radionuclide release from three different WTP glasses (LAWA44, LAWB45 and LAWC22), two different bulk vitrification glasses (6-tank composite and S-109), and three different grout waste forms (containing Silver Iodide, Barium Iodide and Barium Iodate). All WTP and bulk vitrification glasses perform well. However, the radionuclide release from the salt in the cast refractory surrounding the bulk vitrification waste packages is 2 to 170 times higher than the glass release rate, depending on the water recharge rate. Iodine-129 release from grouted waste forms is highly sensitive to the solubility of the iodine compound contained in the grout. The normalized iodine release rate from grout containing barium iodate is a factor of 10 higher than what the normalized release rate would be if the iodine were contained in LAWA44 glass.

  14. Lunar base launch and landing facilities conceptual design

    NASA Technical Reports Server (NTRS)

    Phillips, Paul G.; Simonds, Charles H.; Stump, William R.

    1992-01-01

    The purpose of this study was to perform a first look at the requirements for launch and landing facilities for early lunar bases and to prepared conceptual designs for some of these facilities. The emphasis of the study is on the facilities needed from the first manned landing until permanent occupancy, the Phase 2 lunar base. Factors including surface characteristics, navigation system, engine blast effects, and expected surface operations are used to develop landing pad designs, and definitions fo various other elements of the launch and landing facilities. Finally, the dependence of the use of these elements and the evolution of the facilities are established.

  15. Technical Design of Hadron Therapy Facilities

    SciTech Connect

    Alonso, J.R.

    1993-08-01

    Radiation therapy with hadron beams now has a 40-year track record at many accelerator laboratories around the world, essentially all of these originally physics-research oriented. The great promise shown for treating cancer has led the medical community to seek dedicated accelerator facilities in a hospital setting, where more rapid progress can be made in clinical research. This paper will discuss accelerator and beam characteristics relevant to hadron therapy, particularly as applied to hospital-based facilities. A survey of currently-operating and planned hadron therapy facilities will be given, with particular emphasis on Lorna Linda (the first dedicated proton facility in a hospital) and HIMAC (the first dedicated heavy-ion medical facility).

  16. Technical design of hadron therapy facilities

    SciTech Connect

    Alonso, J.R.

    1993-08-01

    Radiation therapy with hadron beams now has a 40-year track record at many accelerator laboratories around the world, essentially all of these originally physics-research oriented. The great promise shown for treating cancer has led the medical community to seek dedicated accelerator facilities in a hospital setting, where more rapid progress can be made in clinical research. This paper will discuss accelerator and beam characteristics relevant to hadron therapy, particularly as applied to hospital-based facilities. A survey of currently-operating and planned hadron therapy facilities will be given, with particular emphasis on Loma Linda (the first dedicated proton facility in a hospital) and HIMAC (the first dedicated heavy-ion medical facility).

  17. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    SciTech Connect

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  18. Seismic design of low-level nuclear waste repositories and toxic waste management facilities

    SciTech Connect

    Chung, D.H.; Bernreuter, D.L.

    1984-05-08

    Identification of the elements of typical hazardous waste facilities (HFWs) that are the major contributors to the risk are focussed on as the elements which require additional considerations in the design and construction of low-level nuclear waste management repositories and HWFs. From a recent study of six typical HWFs it was determined that the factors that contribute most to the human and environmental risk fall into four basic categories: geologic and seismological conditions at each HWF; engineered structures at each HWF; environmental conditions at each HWF; and nature of the material being released. In selecting and carrying out the six case studies, three groups of hazardous waste facilities were examined: generator industries which treat or temporarily store their own wastes; generator facilities which dispose of their own hazardous wastes on site; and industries in the waste treatment and disposal business. The case studies have a diversity of geologic setting, nearby settlement patterns, and environments. Two sites are above a regional aquifer, two are near a bay important to regional fishing, one is in rural hills, and one is in a desert, although not isolated from nearby towns and a groundwater/surface-water system. From the results developed in the study, it was concluded that the effect of seismic activity on hazardous facilities poses a significant risk to the population. Fifteen reasons are given for this conclusion.

  19. Design criteria for Waste Coolant Processing Facility and preliminary proposal 722 for Waste Coolant Processing Facility

    SciTech Connect

    Not Available

    1991-09-27

    This document contains the design criteria to be used by the architect-engineer (A-E) in the performance of Titles 1 and 2 design for the construction of a facility to treat the biodegradable, water soluble, waste machine coolant generated at the Y-12 plant. The purpose of this facility is to reduce the organic loading of coolants prior to final treatment at the proposed West Tank Farm Treatment Facility.

  20. State waste discharge permit application: 200 Area Treated Effluent Disposal Facility (Project W-049H)

    SciTech Connect

    Not Available

    1994-08-01

    As part of the original Hanford Federal Facility Agreement and Concent Order negotiations, US DOE, US EPA and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground to the Hanford Site are subject to permitting in the State Waste Discharge Permit Program (SWDP). This document constitutes the SWDP Application for the 200 Area TEDF stream which includes the following streams discharged into the area: Plutonium Finishing Plant waste water; 222-S laboratory Complex waste water; T Plant waste water; 284-W Power Plant waste water; PUREX chemical Sewer; B Plant chemical sewer, process condensate, steam condensate; 242-A-81 Water Services waste water.

  1. Interventions for the control of diarrhoeal diseases among young children: improving water supplies and excreta disposal facilities*

    PubMed Central

    Esrey, S. A.; Feachem, R. G.; Hughes, J. M.

    1985-01-01

    A theoretical model is proposed that relates the level of ingestion of diarrhoea-causing pathogens to the frequency of diarrhoea in the community. The implications of this model are that, in poor communities with inadequate water supply and excreta disposal, reducing the level of enteric pathogen ingestion by a given amount will have a greater impact on diarrhoea mortality rates than on morbidity rates, a greater impact on the incidence rate of severe diarrhoea than on that of mild diarrhoea, and a greater impact on diarrhoea caused by pathogens having high infectious doses than on diarrhoea caused by pathogens of a low infectious dose. The impact of water supply and sanitation on diarrhoea, related infections, nutritional status, and mortality is analysed by reviewing 67 studies from 28 countries. The median reductions in diarrhoea morbidity rates are 22% from all studies and 27% from a few better-designed studies. All studies of the impact on total mortality rates show a median reduction of 21%, while the few better-designed studies give a median reduction of 30%. Improvements in water quality have less of an impact than improvements in water availability or excreta disposal. PMID:3878742

  2. Safe Schools Facilities Planner. Improving School Climate and Order through Facilities Design.

    ERIC Educational Resources Information Center

    North Carolina State Dept. of Public Instruction, Raleigh.

    Researchers, consulting professionals, and advocating agencies agree that school facility design is one essential component to a safe and successful school. This document addresses design-related concepts that can positively affect school climate and order. It describes and provides facility planning guidelines for crime prevention through…

  3. Optimization of Waste Disposal - 13338

    SciTech Connect

    Shephard, E.; Walter, N.; Downey, H.; Collopy, P.; Conant, J.

    2013-07-01

    From 2009 through 2011, remediation of areas of a former fuel cycle facility used for government contract work was conducted. Remediation efforts were focused on building demolition, underground pipeline removal, contaminated soil removal and removal of contaminated sediments from portions of an on-site stream. Prior to conducting the remediation field effort, planning and preparation for remediation (including strategic planning for waste characterization and disposal) was conducted during the design phase. During the remediation field effort, waste characterization and disposal practices were continuously reviewed and refined to optimize waste disposal practices. This paper discusses strategic planning for waste characterization and disposal that was employed in the design phase, and continuously reviewed and refined to optimize efficiency. (authors)

  4. A review of geoscience characteristics and disposal experience at the commercial low-level radioactive waste disposal facility near West Valley, New York

    SciTech Connect

    Smoot, J.L.

    1989-08-01

    The West Valley Commercial Low-Level Radioactive Waste disposal site is located about 48 km south of Buffalo, New York. Operation of the site began in 1961 by Nuclear Fuels Service and was terminated in 1975. The disposal trenches at the site are excavated about 5 m into glacial till that has a thickness of about 28 m. About 65,000 m{sup 3} of the waste containing approximately 710,000 Ci were disposed at the site during the operational period. Ground-water movement through the till is predominantly downward as indicated by measurements and numerical simulation of hydraulic head. Radionuclides do not appear to have migrated more than 3 m either laterally or vertically from the waste disposal trenches. Numerical simulations of {sup 3}H, {sup 90}Sr, and {sup 14}C migration are able to reproduce the observed concentration in the till beneath selected trenches. Uncertainty remains with respect to the continuity and heterogeneity of the hydrostratigraphic units and the spatial distribution of hydraulic conductivity and effective porosity. More work is needed to better define the waste inventory and any long-term changes that might be expected. Erosion poses a potential threat to the long-term integrity of the disposal area. 56 refs., 19 figs., 9 tabs.

  5. Design and commissioning experience of SALT facility

    NASA Astrophysics Data System (ADS)

    De Kock, Mariana; Venter, Sarel

    2004-09-01

    The commissioning experience of the facility for SALT is compared to the results of the analysis done during the design. A false steel floor incorporating forced ventilation that extends around the telescope azimuth pier is installed to prevent heat radiating from the concrete surfaces on nights when the ambient temperature drops to below room temperature. An infrared scan was done on this floor to verify that no heat is radiated into the telescope chamber from either the concrete or the warmer rooms underneath. The SALT site is windy all year round, and in order to utilize this natural resource and get better ventilation, adjustable louvers are used for natural ventilation. The control system automatically adjusts the louver openings depending on the wind speed and relative direction of the dome opening to achieve enough air changes during wind still nights. The louvers are throttled to limit windshake on the structure on windy nights. Results of the computational fluid dynamic analysis (CFD) and actual measurements are presented showing adequate temperature distribution at low wind speeds. The correlation between the CFD and actual measurements are discussed, with reference to the surface and air temperatures in the telescope chamber under different ambient conditions. The telescope chamber and dome are built out of insulation panels to limit energy losses during the day when the chamber is air conditioned. It also ensures thermal inertia of the building is low and consequently allows its temperature to react quickly to changes in external ambient temperature. The correlation between the expected and actual capacity of the air conditioners are also discussed.

  6. Geochemical information for the West Chestnut Ridge Central Waste Disposal Facility for low-level radioactive waste

    SciTech Connect

    Seeley, F.G.; Kelmers, A.D.

    1984-06-01

    Geochemical support activities for the Central Waste Disposal Facility (CWDF) project included characterization of site materials, as well as measurement of radionuclide sorption and desorption isotherms and apparent concentration limit values under site-relevant laboratory test conditions. The radionuclide sorption and solubility information is needed as input data for the pathways analysis calculations to model expected radioactivity releases from emplaced waste to the accessible environment under various release scenarios. Batch contact methodology was used to construct sorption and desorption isotherms for a number of radionuclides likely to be present in waste to be disposed of at the site. The sorption rates for uranium and europium were rapid (> 99.8% of the total radionuclide present was adsorbed in approx. 30 min). With a constant-pH isotherm technique, uranium, strontium, cesium, and curium exhibited maximum Rs values of 4800 to > 30,000 L/kg throughout the pH range 5 to 7. Sorption ratios were generally lower at higher or lower pH levels. Retardation factors for uranium, strontium, and cesium, explored by column chromatographic tests, were consistent with the high sorption ratios measured in batch tests for these radionuclides. The addition of as little as 0.01 M organic reagent capable of forming strong soluble complexes with metals (e.g., ethylenediaminetetraacetic acid (EDTA) or citric acid) was found to reduce the sorption ratio for uranium by as much as two orders of magnitude. Substitution of an actual low-level waste site trench water for groundwater in these tests was found to give a similar reduction in the sorption ratio.

  7. 2002 K-12 Educational Facilities Design Awards.

    ERIC Educational Resources Information Center

    Architecture Boston, 2002

    2002-01-01

    Presents eight Boston Society of Architects award-winning educational facilities. Provides information on the architectural and project teams, contractors, and consultants, and includes a brief description and photographs. (EV)

  8. Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record

    SciTech Connect

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2010-10-01

    The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

  9. Petroleum Fuel Facilities. Design Manual 22.

    DTIC Science & Technology

    1982-08-01

    may be com- bined with containments or treatment facilities of other areas. If the loading rack is protected by a fire water or foam system, the...2,500 gal/min. It is desirable to have a relatively unlimited supply of fire water , as from a natural waterway or large reservoir. b. Foam Systems...Operational Facilities. All piers should be protected by fire water systems with hydrants located so that vessels alongside can be reached through hose

  10. 40 CFR 60.30d - Designated facilities.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emissions Guidelines and Compliance Times for Sulfuric Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  11. 40 CFR 60.30d - Designated facilities.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emissions Guidelines and Compliance Times for Sulfuric Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  12. 40 CFR 60.30d - Designated facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emissions Guidelines and Compliance Times for Sulfuric Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  13. 40 CFR 60.30d - Designated facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emissions Guidelines and Compliance Times for Sulfuric Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  14. 40 CFR 60.30d - Designated facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) STANDARDS OF PERFORMANCE FOR NEW STATIONARY SOURCES Emissions Guidelines and Compliance Times for Sulfuric Acid Production Units § 60.30d Designated facilities. Sulfuric acid production units. The designated facility to which §§ 60.31d and 60.32d apply is each existing “sulfuric acid production unit” as defined in...

  15. Designing for Education: Compendium of Exemplary Educational Facilities 2011

    ERIC Educational Resources Information Center

    OECD Publishing (NJ3), 2011

    2011-01-01

    "Designing for Education: Compendium of Exemplary Educational Facilities 2011" showcases over 60 recently built or refurbished educational facilities from 28 countries. Collectively, these projects demonstrate state-of-the-art design in this field and each one is lavishly illustrated with colour photos, plans and descriptions. [A free PDF is…

  16. Designing for Education: Compendium of Exemplary Educational Facilities 2011

    ERIC Educational Resources Information Center

    OECD Publishing (NJ3), 2011

    2011-01-01

    "Designing for Education: Compendium of Exemplary Educational Facilities 2011" showcases over 60 recently built or refurbished educational facilities from 28 countries. Collectively, these projects demonstrate state-of-the-art design in this field and each one is lavishly illustrated with colour photos, plans and descriptions. [A free PDF is…

  17. 42 CFR 9.4 - Physical facility policies and design.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... STANDARDS OF CARE FOR CHIMPANZEES HELD IN THE FEDERALLY SUPPORTED SANCTUARY SYSTEM § 9.4 Physical facility policies and design. (a) What standards apply to the facility design and physical plant? The chimpanzee... to accommodate natural activities of chimpanzees while restricting their movement and range to the...

  18. 42 CFR 9.4 - Physical facility policies and design.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... STANDARDS OF CARE FOR CHIMPANZEES HELD IN THE FEDERALLY SUPPORTED SANCTUARY SYSTEM § 9.4 Physical facility policies and design. (a) What standards apply to the facility design and physical plant? The chimpanzee... to accommodate natural activities of chimpanzees while restricting their movement and range to the...

  19. 42 CFR 9.4 - Physical facility policies and design.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... STANDARDS OF CARE FOR CHIMPANZEES HELD IN THE FEDERALLY SUPPORTED SANCTUARY SYSTEM § 9.4 Physical facility policies and design. (a) What standards apply to the facility design and physical plant? The chimpanzee... to accommodate natural activities of chimpanzees while restricting their movement and range to the...

  20. 42 CFR 9.4 - Physical facility policies and design.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... STANDARDS OF CARE FOR CHIMPANZEES HELD IN THE FEDERALLY SUPPORTED SANCTUARY SYSTEM § 9.4 Physical facility policies and design. (a) What standards apply to the facility design and physical plant? The chimpanzee... to accommodate natural activities of chimpanzees while restricting their movement and range to...