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581 Matching Results
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The Clifton Record (Clifton, Tex.), Vol. 107, No. 51, Ed. 1 Wednesday, June 26, 2002
Semi-weekly newspaper from Clifton, Texas that includes local, state, and national news along with advertising.
Date:
June 26, 2002
Creator:
Smith, W. Leon
Object Type:
Newspaper
System:
The Portal to Texas History
The Clifton Record (Clifton, Tex.), Vol. 107, No. 60, Ed. 1 Friday, July 26, 2002
Semi-weekly newspaper from Clifton, Texas that includes local, state, and national news along with advertising.
Date:
July 26, 2002
Creator:
Smith, W. Leon
Object Type:
Newspaper
System:
The Portal to Texas History
Polk County Enterprise (Livingston, Tex.), Vol. 120, No. 77, Ed. 1 Thursday, September 26, 2002
Semi-weekly newspaper from Livingston, Texas that includes local, state and national news along with advertising.
Date:
September 26, 2002
Creator:
White, Barbara
Object Type:
Newspaper
System:
The Portal to Texas History
Hondo Anvil Herald (Hondo, Tex.), Vol. 116, No. 39, Ed. 1 Thursday, September 26, 2002
Weekly newspaper from Hondo, Texas that includes local, state, and national news along with extensive advertising.
Date:
September 26, 2002
Creator:
unknown
Object Type:
Newspaper
System:
The Portal to Texas History
Hondo Anvil Herald (Hondo, Tex.), Vol. 116, No. 52, Ed. 1 Thursday, December 26, 2002
Weekly newspaper from Hondo, Texas that includes local, state, and national news along with extensive advertising.
Date:
December 26, 2002
Creator:
unknown
Object Type:
Newspaper
System:
The Portal to Texas History
Texas Jewish Post (Fort Worth, Tex.), Vol. 56, No. 52, Ed. 1 Thursday, December 26, 2002
Weekly Jewish newspaper from Fort Worth, Texas that includes local, state, and national news along with extensive advertising.
Date:
December 26, 2002
Creator:
Wisch, Rene
Object Type:
Newspaper
System:
The Portal to Texas History
Building 7602 Decontamination and Decommissioning for Reuse by Spallation Neutron Source
Building 7602 at the Oak Ridge National Laboratory (ORNL) was constructed in 1963 as a Reactor Service Building for the Experimental Gas-Cooled Reactor; the reactor was never fueled or operated, and the project was terminated in 1965. Significant building modifications were performed during the late 1970s and early 1980s. Beginning in 1984, separation processes and equipment development and testing were initiated for the Consolidated Fuel Reprocessing Program (CFRP). The principal materials used in the processes were depleted and natural uranium, nitric acid, and organic solvents. CFRP operations continued until 1994 when the program was discontinued and the facility declared surplus to the U.S. Department of Energy (DOE). Systems and equipment were shut down; feed and waste materials were removed; and process fluids, chemicals, and uranium were drained and flushed from systems. This paper will present an overview of the Building 7602 D&D activities, final radiological survey , facility modifications, and project interfaces.
Date:
February 26, 2002
Creator:
Brill, A.; Berger, J.; Kelsey, A. & Plummer, K.
Object Type:
Article
System:
The UNT Digital Library
Reliability and Consistency of Surface Contamination Measurements
Surface contamination evaluation is a tough problem since it is difficult to isolate the radiations emitted by the surface, especially in a highly irradiating atmosphere. In that case the only possibility is to evaluate smearable (removeable) contamination since ex-situ countings are possible. Unfortunately, according to our experience at CEA, these values are not consistent and thus non relevant. In this study, we show, using in-situ Fourier Transform Infra Red spectrometry on contaminated metal samples, that fixed contamination seems to be chemisorbed and removeable contamination seems to be physisorbed. The distribution between fixed and removeable contamination appears to be variable. Chemical equilibria and reversible ion exchange mechanisms are involved and are closely linked to environmental conditions such as humidity and temperature. Measurements of smearable contamination only give an indication of the state of these equilibria between fixed and removeable contamination at the time and in the environmental conditions the measurements were made.
Date:
February 26, 2002
Creator:
Rouppert, F.; Rivoallan, A. & Largeron, C.
Object Type:
Article
System:
The UNT Digital Library
Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site
In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.
Date:
February 26, 2002
Creator:
Church, A.; Gordon, J. & Montrose, J. K.
Object Type:
Article
System:
The UNT Digital Library
An Alternative to Performing Remote-Handled Transuranic Waste Container Headspace Gas Sampling and Analysis
The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the …
Date:
February 26, 2002
Creator:
Spangler, L. R.; Djordjevic, S. M.; Kehrman, R. F. & Most, W. A.
Object Type:
Article
System:
The UNT Digital Library
Removal of Radioactive Nuclides by Multi-Functional Microcapsules Enclosing Inorganic Ion-Exchangers and Organic Extractants
The microcapsules enclosing two kinds of functional materials, inorganic ion-exchangers and organic extractants, were prepared by taking advantage of the high immobilization ability of alginate gel polymer. The fine powders of inorganic ion-exchanger and oil drops of extractant were kneaded with sodium alginate (NaALG) solution and the kneaded sol readily gelled in a salt solution of CaCl2, BaCl2 or HCl to form spherical gel particles. The uptake properties of various nuclides, 137Cs, 85Sr, 60Co, 88Y, 152Eu and 241Am, for thirty-four specimens of microcapsules in the presence of 10-1-10-4 M HNO3 were evaluated by the batch method. The distribution coefficient (Kd) of Cs+ above 103 cm3/g was obtained for the microcapsules enclosing CuFC or AMP. The Kd of Sr2+ around 102 cm3/g was obtained for the microcapsules containing clinoptilolite, antimonic acid, zeolite A, zeolite X or titanic acid. The microcapsules enclosing DEHPA exhibited relatively large Kd values of trivalent metal ions above 103 cm3/g; for example, the Kd values of Cs+, Sr2+, Co2+, Y3+, Eu3+ and Am3+ for a favorable microcapsule (CuFC/clinoptilolite/DEHPA/CaALG) were 1.1x104, 7.5x10, 1.1x10, 1.0x104, 1.4x104, 3.4x103 cm3/g, respectively. The uptake rates of Cs+, Y3+, Eu3+ and Am3+ for this microcapsule were rather fast; the uptake percentage above 90% …
Date:
February 26, 2002
Creator:
Mimura, H.; Akiba, K. & Onodera, Y.
Object Type:
Article
System:
The UNT Digital Library
Integrating Risk Analyses and Tools at the U.S. Department of Energy Hanford Site
Risk assessment and environmental impact analysis at the U.S. Department of Energy (DOE) Hanford Site in Washington State has made significant progress in refining the strategy for using risk analysis to support closing of several hundred waste sites plus 149 single-shell tanks at the Hanford Site. A Single-Shell Tank System Closure Work Plan outlines the current basis for closing the single-shell tank systems. An analogous site approach has been developed to address closure of aggregated groups of similar waste sites. Because of the complexity, decision time frames, proximity of non-tank farm waste sites to tank farms, scale, and regulatory considerations, various projects are providing integrated assessments to support risk analyses and decision-making. This paper will describe the approach for using risk assessment to support waste site and tank closure decisions, the tools being developed, and how integration of these risk assessments and analyses are being performed to ad dress near-term and longterm decisions.
Date:
February 26, 2002
Creator:
Lober, R. W.; Yasek, R. M.; Morse, J. G.; Buck, J. W.; Henderson, C. C.; Sams, T. L. et al.
Object Type:
Article
System:
The UNT Digital Library
Supplemental Performance Analyses for Igneous Activity and Human Intrusion at the Potential High-Level Nuclear Waste Repository at Yucca Mountain
The U.S. Department of Energy (DOE) is considering the possible recommendation of a site at Yucca Mountain, Nevada, for the potential development of a geologic repository for the disposal of high-level radioactive waste and spent nuclear fuel. Consequences of hypothetical disruption of the Yucca Mountain site by igneous activity or human intrusion have been evaluated in the Yucca Mountain Science and Engineering Report (S&ER) (1), which presents technical information supporting the consideration of the possible site recommendation. Since completion of the S&ER, supplemental analyses have examined possible impacts of new information and alternative assumptions on the estimates of the consequences of these events. Specifically, analyses of the consequences of igneous disruption address uncertainty regarding: (1) the impacts of changes in the repository footprint and waste package spacing on the probability of disruption; (2) impacts of alternative assumptions about the appropriat e distribution of future wind speeds to use in the analysis; (3) effects of alternative assumptions about waste particle sizes; and (4) alternative assumptions about the number of waste packages damaged by igneous intrusion; and (5) alternative assumptions about the exposure pathways and the biosphere dose conversion factors used in the analysis. Additional supplemental analyses, supporting the Final Environmental Impact …
Date:
February 26, 2002
Creator:
Swift, P.; Gaither, K.; Freeze, G.; McCord, J.; Kalinich, D.; Saulnier, G. et al.
Object Type:
Article
System:
The UNT Digital Library
Technical Evaluations of Proposed Remote-Handled Transuranic Waste Characterization Requirements at WIPP
Characterization, packaging, transport, handling and disposal of remotely handled transuranic (RH TRU) waste at WIPP will be different than similar operations with contact handled transuranic (CH TRU) waste. This paper presents results of technical evaluations associated with the planned disposal of remotely handled transuranic waste at the Waste Isolation Pilot Plant (WIPP).
Date:
February 26, 2002
Creator:
Anastas, G. & Channell, J. K.
Object Type:
Article
System:
The UNT Digital Library
Oak Ridge National Laboratory Management & Integration Perspective Subcontractors as Partners in Site Restoration
In 1997, the U. S. Department of Energy (DOE) Oak Ridge Operations (ORO) Office awarded the Management and Integration (M&I) contract for all five of their Oak Ridge Operations facilities to Bechtel Jacobs Company, LLC (BJC). This paper will focus on the success and challenges of several of the M&I projects at the Oak Ridge National Laboratory (ORNL). The initial goals for BJC were to transition up to 93% of their staff to the subcontract community as they moved away from operations to ''integration.'' The perspectives of BJC and one of their Remedial Action/Decontamination & Decommissioning (RADD) subcontractors will be combined in this paper to share with others how ''partnering'' together was essential for success. Projects completed by Safety and Ecology Corporation (SEC) under their RADD subcontract will be used to illustrate the process and the challenges/successes to completion. These projects will include pond remediation, tank remediation, and building cleanup for reuse. All these projects were ''fixed price'' with defined milestones keyed into award fee for BJC and regulatory milestones for DOE. By working together to form integrated teams focused on site remediation without sacrificing safety, all milestones were met. This paper will discuss the following items associated with the …
Date:
February 26, 2002
Creator:
Brill, A. & Eidam, G.
Object Type:
Article
System:
The UNT Digital Library
Low-Temperature, Anode-Supported High Power Density Solid Oxide Fuel Cells With Nanostructured Electrodes
Anode-supported cells comprising Ni + yttria-stabilized zirconia (YSZ) anode, thin ({approx}10 {micro}m) YSZ electrolyte, and composite cathodes containing a mixture of La{sub 0.8}Sr{sub 0.2}MnO{sub (3-{delta})} (LSM) and La{sub 0.9}Sr{sub 0.1}Ga{sub 0.8}Mg{sub 0.2}O{sub (3-{lambda})} (LSGM) were fabricated. The relative proportions of LSGM and LSM were varied between 30 wt.% LSGM + 70 wt.% LSM and 70 wt.% LSGM + 30 wt.% LSM, while the firing temperature was varied between 1000 and 1200 C. The cathode interlayer composition had a profound effect on cathode performance at 800 C with overpotentials ranging between 60 and 425 mV at 1.0 A/cm{sup 2} and exhibiting a minimum for 50 wt.% LSGM + 50 wt.% LSM. The cathodic overpotential decreased with increasing firing temperature of the composite interlayer in the range 1000 {le} T {le} 1150 C, and then increased dramatically for the interlayer fired at 1200 C. The cell with the optimized cathode interlayer of 50 wt.% LSM + 50 wt.% LSGM fired at 1150 C exhibited an area specific cell resistance of 0.18 {Omega}cm{sup 2} and a maximum power density of 1.4 W/cm{sup 2} at 800 C. Chemical analysis revealed that LSGM reacts with YSZ above 1000 C to form the pyrochlore phase, La{sub …
Date:
March 26, 2002
Creator:
Virkar, Anil V.
Object Type:
Report
System:
The UNT Digital Library
Parametric Analyses of Alternative Flow Models at Yucca Mountain, Nevada Calibrations and Controls - State of Nevada-Funded Research
The controls on the potentiometric surface and temperature distribution at Yucca Mountain have long been thought to be related to major fault zones. The exact way the faults influence these distributions has been somewhat elusive. The parametric studies discussed in this paper show that the fault zone x, y and z permeability tensors, as well as the alignment of the fault zone in relation to the flow field (1), are major contributing factors in the pressure and temperature distributions. A series of runs were conducted for the State of Nevada with a 3-dimensional model utilizing the AT2VOC version of the A-TOUGH code (2),(3). The runs were conducted under steady state conditions and utilized fully coupled heat and flow conditions. The model setup and boundary conditions are fully described. Comparisons were done with varying degrees of anisotropic permeability ratios in the fault zones. The resulting temperature and pressure profiles are compared. The model, while simple, allowed us to examine the relationship of the head and temperature distributions to the position and permeability of major fault zones. It is our conclusion that the major faults included in this model do significantly affect the observed head and temperature distributions. Performance Assessments currently may …
Date:
February 26, 2002
Creator:
Lehman, L. & Brown, T. P.
Object Type:
Article
System:
The UNT Digital Library
The Murmansk Initiative - RF: Acceptance Testing
The Murmansk Initiative-RF (MI) was conceived to provide the Russian Federation (RF) with the capacity to manage low-level liquid radioactive waste (LLRW) and comply with the requirements of the London Convention that prohibit ocean dumping. The trilateral project among Norway, the RF, and the United States of America (U.S.) began in 1994 and was the first to utilize exclusively Russian subcontractors to upgrade and expand an existing LLRW treatment plant on the premises of RTP Atomflot in Murmansk, Russia. The project moved quickly through the design phase. Progress during the construction phase was somewhat slower because of difficulties with acquisition of hardware, inexperience with automated instrumentation and control equipment, and unexpected design changes in the cementation unit. The project advanced into the test-operation phase, which is currently underway, in June 2001. Initial runs with liquid waste have revealed that procedures for unloading spent ion-exchange sorbents could be improved and that sludges formed during removal of alkaline-earth metals should be compacted in order for the facility to operate at its full potential. Resolution of these issues is expected within the next few months.
Date:
February 26, 2002
Creator:
Czajkowski, C.; Wester, D. W.; Dyer, R. S.; Soerlie, A. A.; Moller, B. & Barnes, E.
Object Type:
Article
System:
The UNT Digital Library
Waste Issues Associated with the Safe Movement of Hazardous Chemicals
Moving hazardous chemicals presents the risk of exposure for workers engaged in the activity and others that might be in the immediate area. Adverse affects are specific to the chemicals and can range from minor skin, eye, or mucous membrane irritation, to burns, respiratory distress, nervous system dysfunction, or even death. A case study is presented where in the interest of waste minimization; original shipping packaging was removed from a glass bottle of nitric acid, while moving corrosive liquid through a security protocol into a Radiological Control Area (RCA). During the transfer, the glass bottle broke. The resulting release of nitric acid possibly exposed 12 employees with one employee being admitted overnight at a hospital for observation. This is a clear example of administrative controls to reduce the generation of suspect radioactive waste being implemented at the expense of employee health. As a result of this event, material handling procedures that assure the safe movement of hazardous chemicals through a security protocol into a radiological control area were developed. Specifically, hazardous material must be transferred using original shipping containers and packaging. While this represents the potential to increase the generation of suspect radioactive waste in a radiological controlled area, arguments …
Date:
February 26, 2002
Creator:
Dare, Jeffrey H. & Cournoyer, Michael E.
Object Type:
Article
System:
The UNT Digital Library
Using FEP's List and a PA Methodology for Evaluating Suitable Areas for the LLW Repository in Italy
In Italy following a referendum held in 1987, nuclear energy has been phased out. Since 1998, a general site selection process covering the whole Italian territory has been under way. A GIS (Geographic Information System) methodology was implemented in three steps using the ESRI Arc/Info and Arc/View platforms. The screening identified approximately 0.8% of the Italian territory as suitable for locating the LLW Repository. 200 areas have been identified as suitable for the location of the LLW Repository, using a multiple exclusion criteria procedure (1:500,000), regional scale (1:100.000) and local scale (1:25,000-1:10,000). A methodology for evaluating these areas has been developed allowing, along with the evaluation of the long term efficiency of the engineered barrier system (EBS), the characterization of the selected areas in terms of physical and safety factors and planning factors. The first step was to identify, on a referenced FEPs list, a group of geomorphological, geological, hydrogeological, climatic and human behavior caused process and/or events, which were considered of importance for the site evaluation, taking into account the Italian situation. A site evaluation system was established ascribing weighted scores to each of these processes and events, which were identified as parameters of the new evaluation system. The …
Date:
February 26, 2002
Creator:
Risoluti, P.; Ciabatti, P. & Mingrone, G.
Object Type:
Article
System:
The UNT Digital Library
Minimizing Waste from the Oil Industry: Scale Treatment and Scrap Recycling
Naturally occurring radioactive material is technologically concentrated in the piping in systems in the oil and gas industry, especially in the offshore facilities. The activity, mainly Ra-226, in the scales in the systems are often at levels classified as low level radioactive waste (LSA) in the industry. When the components and pipes are descaled for maintenance or recycling purposes, usually by high-pressure water jetting, the LSA scales arising constitute a significant quantity of radioactive waste for disposal. A new process is under development for the treatment of scales, where the radioactive solids are separated from the inactive. This would result in a much smaller fraction to be deposited as radioactive waste. The radioactive part recovered from the scales will be reduced to a stable non-metallic salt and because the volume is significantly smaller then the original material, will minimize the cost for disposal. The pipes, that have been cleaned by high pressure water jetting can either be reused or free released by scrapping and melting for recycling.
Date:
February 26, 2002
Creator:
Lindberg, M.
Object Type:
Article
System:
The UNT Digital Library
Deployment of Smart 3D Subsurface Contaminant Characterization at the Brookhaven Graphite Research Reactor
The Brookhaven Graphite Research Reactor (BGRR) Historical Site Assessment (BNL 1999) identified contamination inside the Below Grade Ducts (BGD) resulting from the deposition of fission and activation products from the pile on the inner carbon steel liner during reactor operations. Due to partial flooding of the BGD since shutdown, some of this contamination may have leaked out of the ducts into the surrounding soils. The baseline remediation plan for cleanup of contaminated soils beneath the BGD involves complete removal of the ducts, followed by surveying the underlying and surrounding soils, then removing soil that has been contaminated above cleanup goals. Alternatively, if soil contamination around and beneath the BGD is either non-existent/minimal (below cleanup goals) or is very localized and can be ''surgically removed'' at a reasonable cost, the BGD can be decontaminated and left in place. The focus of this Department of Energy Accelerated Site Technology Deployment (DOE ASTD) project was to determine the extent (location, type, and level) of soil contamination surrounding the BGD and to present this data to the stakeholders as part of the Engineering Evaluation/Cost Analysis (EE/CA) process. A suite of innovative characterization tools was used to complete the characterization of the soil surrounding the …
Date:
February 26, 2002
Creator:
Sullivan, T.; Heiser, J.; Kalb, P.; Milian, L.; Newson, C.; Lilimpakas, M. et al.
Object Type:
Article
System:
The UNT Digital Library
Office of River Protection Mission Completion Strategy
DOE's Office of River Protection (ORP) is readying itself to commence construction of a Waste Treatment Plant (WTP) that will start the process of turning Hanford tank waste into glass. The plant is state-of-the art and includes reasonable flexibility to improve operations as technology and operational understandings improve. During its 40 year design life the plant has the capability to treat half of the total volume of tank waste and reduce risk to the public by up to ninety percent. Looking beyond initial processing towards the project end state, however, it is apparent that ORP's baseline approach is part of the issue raised by the DOE Secretary when he said that $300 billion and 75 years is too costly and too long for DOE's environmental cleanups. ORP has reviewed its cost and schedule drivers and has started identifying areas where better technologies and risk-based strategies could substantially decrease its life cycle cost and schedule. Specific technologies under consideration will be discussed along with expected return on investment. ORP is totally committed to taking all steps necessary during cleanup to protect human health and the environment and to comply with appropriate regulations and commitments. But, ORP is also very conscious of …
Date:
February 26, 2002
Creator:
Wiegman, S. A.; Hewitt, W. M.; Yuracko, K. & Holbrook, J. H.
Object Type:
Article
System:
The UNT Digital Library
Progress on Cleaning Up the Only Commercial Nuclear Fuel Reprocessing Facility to Operate in the United States
This paper describes the progress on cleanup of the West Valley Demonstration Project (WVDP), an environmental management project located south of Buffalo, NY. The WVDP was the site of the only commercial nuclear fuel reprocessing facility to have operated in the United States (1966 to 1972). Former fuel reprocessing operations generated approximately 600,000 gallons of liquid high-level radioactive waste stored in underground tanks. The U.S. Congress passed the WVDP Act in 1980 (WVDP Act) to authorize cleanup of the 220-acre facility. The facility is unique in that it sits on the 3,345-acre Western New York Nuclear Service Center (WNYNSC), which is owned by New York State through the New York State Energy Research and Development Authority (NYSERDA). The U.S. Department of Energy (DOE) has overall responsibility for the cleanup that is authorized by the WVDP Act, paying 90 percent of the WVDP costs; NYSERDA pays 10 percent. West Valley Nuclear Services Company (WVNSCO) is the management contractor at the WVDP. This paper will provide a description of the many accomplishments at the WVDP, including the pretreatment and near completion of vitrification of all the site's liquid high-level radioactive waste, a demonstration of technologies to characterize the remaining material in the …
Date:
February 26, 2002
Creator:
Jackson, T. J.; MacVean, S. A. & Szlis, K. A.
Object Type:
Article
System:
The UNT Digital Library