Resource Type
Partner
Collection
Office of Scientific & Technical Information Technical Reports
5,818
Congressional Research Service Reports
736
Texas State Publications
89
Texas State Auditor's Office: Reports
83
Technical Report Archive and Image Library
10
D. Jack Davis Art Education Collection
9
Government Accountability Office Reports
9
LGBT Collections
6
Texas Human Rights Foundation Collection (The Dallas Way)
5
End of Term Publications
4
6 More
Serial/Series Title
Fiscal Year 1998
45
105th Congress
39
Fiscal Year 1999
34
Fiscal Year 1997
29
Texas Motor Vehicle Traffic Accident Summaries
16
Construction and Maintenance Report
12
Texas Department of Transportation Contract Reports
12
Texas Real Estate Center Trends
12
San Antonio Board of Adjustment Monthly Report
6
San Antonio Monthly Permit Report
6
97 More
Degree Department
Country
States
Year
Month
Language
Results:
1 - 24 of
6,769
next
2-D linear motion system. Innovative technology summary report
The US Department of Energy's (DOE's) nuclear facility decontamination and decommissioning (D and D) program requires buildings to be decontaminated, decommissioned, and surveyed for radiological contamination in an expeditious and cost-effective manner. Simultaneously, the health and safety of personnel involved in the D and D activities is of primary concern. D and D workers must perform duties high off the ground, requiring the use of manlifts or scaffolding, often, in radiologically or chemically contaminated areas or in areas with limited access. Survey and decontamination instruments that are used are sometimes heavy or awkward to use, particularly when the worker is operating from a manlift or scaffolding. Finding alternative methods of performing such work on manlifts or scaffolding is important. The 2-D Linear Motion System (2-D LMS), also known as the Wall Walker{trademark}, is designed to remotely position tools and instruments on walls for use in such activities as radiation surveys, decontamination, and painting. Traditional (baseline) methods for operating equipment for these tasks require workers to perform duties on elevated platforms, sometimes several meters above the ground surface and near potential sources of contamination. The Wall Walker 2-D LMS significantly improves health and safety conditions by facilitating remote operation of equipment. …
Date:
November 1, 1998
Creator:
unknown
System:
The UNT Digital Library
3-D Spectral IP Imaging: Non-Invasive Characterization of Contaminant Plumes
The overall objective of this project is to develop the scientific basis for characterizing contaminant plumes in the earth's subsurface using field measurements of induced polarization (IP) effects. Three specific objectives towards this end are: (1) Understanding IP at the laboratory level through measurements of complex resistivity as a function of frequency in rock and soil samples with varying pore geometries, pore fluid conductivities and saturations, and contaminant chemistries and concentrations. (2) Developing effective data acquisition techniques for measuring the critical IP responses (time domain or frequency domain) in the field. (3) Developing modeling and inversion algorithms that permit the interpretation of field IP data in terms of subsurface geology and contaminant plume properties.
Date:
June 1, 1998
Creator:
Morgan, F. Dale; Rodi, William & Lesmes, David
System:
The UNT Digital Library
3-D Spectral IP Imaging: Non-Invasive Characterization of Contaminant Plumes. 1998 Annual Progress Report
'The overall objective of this project is to develop the scientific basis for characterizing contaminant plumes in the earth''s subsurface using field measurements of induced polarization (IP) effects. Three specific objectives towards this end are: (1) understanding IP at the laboratory level through measurements of complex resistivity as a function of frequency in rock and soil samples with varying pore geometries, pore fluid conductivities and saturations, and contaminant chemistries and concentrations; (2) developing effective data acquisition techniques for measuring the critical IP responses (time domain or frequency domain) in the field; (3) developing modeling and inversion algorithms that permit the interpretation of field IP data in terms of subsurface geology and contaminant plume properties. The authors laboratory experiments to date are described in Appendices A and B, which consist of two papers submitted to the annual SAGEEP conference (Frye et al., 1998; Sturrock et al., 1998). The experiments involved measurements of complex resistivity vs. frequency on a suite of brine saturated sandstone samples. In one set of experiments, the fluid chemistry (pH, ionic strength, and cation type) was varied. In a second set of experiments, the microgeometry of the rock matrix was varied. The experiments showed that spectral IP responses …
Date:
June 1, 1998
Creator:
Morgan, F. D.; Rodi, W. & Lesmes, D.
System:
The UNT Digital Library
25. anniversary of the 1973 oil embargo: Energy trends since the first major U.S. energy crisis
The purpose of this publication is not to assess the causes of the 1973 energy crisis or the measures that were adopted to resolve it. The intent is to present some data on which such analyses can be based. Many of the trends presented here fall into two distinct periods. From 1973 to the mid-1980`s, prices continued at very high levels, in part because of a second oil shock in 1979--80. During this period, rapid progress was made in raising American oil production, reducing dependence on oil imports, and improving end-use efficiency. After the oil price collapse of the mid-1980`s, however, prices retreated to more moderate levels, the pace of efficiency gains slowed, American oil production fell, and the share of imports rose. 30 figs.
Date:
August 1, 1998
Creator:
unknown
System:
The UNT Digital Library
105-K Basin material design basis feed description for spent nuclear fuel project facilities
Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.
Date:
January 8, 1998
Creator:
Praga, A. N.
System:
The UNT Digital Library
105-K Basin material design basis feed description for spent nuclear fuel project facilities. Volume 2: Sludge
Volume 2 provides the design feed compositions for the baseline K East and K West Basin sludge process streams expected to be generated during Spent Nuclear Fuel (SNF) Project activities. Four types of feeds are required to support evaluation of specific facility and process considerations during the development of new facilities and processes. These four design feeds provide nominal and bounding conditions for design evaluations. Volume 2 includes definition of inventories for: (1) KE and KW Basins sludge locations (pit sludges, floor sludge, canister.sludge, and wash sludge components), (2) nominal feed for each of five process feed streams, (3) shielding design feed, (4) safety/regulatory assessment feed, and (5) criticality assessment feed.
Date:
August 30, 1998
Creator:
Pearce, K. L.
System:
The UNT Digital Library
200 Area effluent treatment facility process control plan 98-02
This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP).
Date:
January 30, 1998
Creator:
Le, Elvis Q.
System:
The UNT Digital Library
209-E Building -- Response to ventilation failure evaluation
This document provides an evaluation and recommendations for radiological workplace air monitoring and response to ventilation failure for the Critical Mass Laboratory, 209-E Building. The Critical Mass Laboratory, part of the 209-E Building, was designed to provide a heavily shielded room where plutonium and uranium liquid solutions could be brought into various critical configurations under readily controlled and monitored conditions. The facility is contained within a one-story L-shaped concrete block and reinforced concrete building. One wing houses offices, a control room, shops, and a common area while the other wing includes an equipment room, the change room, work areas, and the two-story Critical Assembly Room (CAR). Three of the rooms contain radiologically contaminated equipment and materials.
Date:
July 27, 1998
Creator:
Foust, D.J.
System:
The UNT Digital Library
221-U Facility concrete and reinforcing steel evaluations specification for the canyon disposition initiative (CDI)
This describes a test program to establish the in-situ material properties of the reinforced concrete in Building 221-U for comparison to the original design specifications. Field sampling and laboratory testing of concrete and reinforcing steel structural materials in Building 221-U for design verification will be undertaken. Forty seven samples are to be taken from radiologically clean exterior walls of the canyon. Laboratory testing program includes unconfined compressive strength of concrete cores, tensile strength of reinforcing steel, and petrographic examinations of concrete cores taken from walls below existing grade.
Date:
May 28, 1998
Creator:
Baxter, J. T.
System:
The UNT Digital Library
300 area TEDF permit compliance monitoring plan
This document presents the permit compliance monitoring plan for the 300 Area Treated Effluent Disposal Facility (TEDF). It addresses the compliance with the National Pollutant Discharge Elimination System (NPDES) permit and Department of Natural Resources Aquatic Lands Sewer Outfall Lease.
Date:
November 20, 1998
Creator:
BERNESKI, L.D.
System:
The UNT Digital Library
303-K Storage Facility report on FY98 closure activities
This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined …
Date:
July 17, 1998
Creator:
Adler, J. G.
System:
The UNT Digital Library
324/327 facilities environmental effluent specifications
These effluent technical specifications address requirements for the 324/327 facilities, which are undergoing stabilization activities. Effluent technical specifications are imposed to protect personnel, the environment and the public, by ensuring adequate implementation and compliance with federal and state regulatory requirements and Hanford programs.
Date:
October 29, 1998
Creator:
JOHNSON, D.L.
System:
The UNT Digital Library
324 and 327 essential drawing list
The purpose of this document is to publish a list of essential drawings for the 324 and 327 Facilities. The report consists of a list of engineering drawings, not the drawings themselves.
Date:
May 21, 1998
Creator:
Spencer, R. H.
System:
The UNT Digital Library
324 Building fire hazards analysis implementation plan
In March 1998, the 324 Building Fire Hazards Analysis (FHA) (Reference 1) was approved by the US Department of Energy, Richland Operations Office (DOE-RL) for implementation by B and W Hanford Company (BWHC). The purpose of the FHA was to identify gaps in compliance with DOE Order 5480.7A (Reference 2) and Richland Operations Office Implementation Directive (RLID) 5480.7 (Reference 3), especially in regard to loss limitation. The FHA identified compliance gaps in six areas and provided 20 recommendations to bring the 324 Building into compliance with DOE Order 5480.7A. Additionally, one observation was provided. To date, four of the recommendations and the one observation have been completed. Actions identified for seven of the recommendations are currently in progress. Exemption requests will be transmitted to DOE-RL for three of the recommendations. Six of the recommendations are related to future shut down activities of the facility and the corrective actions are not being addressed as part of this plan. The actions for recommendations associated with the safety related part of the 324 Building and operation of the cells and support areas were evaluated using the Unreviewed Safety Question (USQ) process. Major Life Safety Code concerns have been corrected. The status of the …
Date:
September 16, 1998
Creator:
Eggen, C.D.
System:
The UNT Digital Library
324 Building liquid waste handling and removal system project plan
This report evaluates the modification options for handling radiological liquid waste generated during decontamination and cleanout of the 324 Building. Recent discussions indicate that the Hanford site railroad system will be closed by the end of FY 1998 necessitating the need for an alternate transfer method. The issue of handling of Radioactive Liquid Waste (RLW) from the 324 Building (assuming the 340 Facility is not available to accept the RLW) has been examined in at least two earlier engineering studies (Parsons 1997a and Hobart 1997). Each study identified a similar preferred alternative that included modifying the 324 Building RLWS to allow load-out of wastewater to a truck tanker, while making maximum use of existing piping, tanks, instrumentation, controls and other features to minimize costs and physical changes to the building. This alternative is accepted as the basis for further discussion presented in this study. The goal of this engineering study is to verify the path forward presented in the previous studies and assure that the selected alternative satisfies the 324 Building deactivation goals and objectives as currently described in the project management plan. This study will also evaluate options available to implement the preferred alternative and select the preferred option …
Date:
July 29, 1998
Creator:
Ham, J.E.
System:
The UNT Digital Library
324 Building radiochemical engineering cells, high-level vault, low-level vault, and associated areas closure plan
The Hanford Site, located adjacent to and north of Richland, Washington, is operated by the US Department of Energy, Richland Operations Office (RL). The 324 Building is located in the 300 Area of the Hanford Site. The 324 Building was constructed in the 1960s to support materials and chemical process research and development activities ranging from laboratory/bench-scale studies to full engineering-scale pilot plant demonstrations. In the mid-1990s, it was determined that dangerous waste and waste residues were being stored for greater than 90 days in the 324 Building Radiochemical Engineering Cells (REC) and in the High-Level Vault/Low-Level Vault (HLV/LLV) tanks. [These areas are not Resource Conservation and Recovery Act of 1976 (RCRA) permitted portions of the 324 Building.] Through the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-89, agreement was reached to close the nonpermitted RCRA unit in the 324 Building. This closure plan, managed under TPA Milestone M-20-55, addresses the identified building areas targeted by the Tri-Party Agreement and provides commitments to achieve the highest degree of compliance practicable, given the special technical difficulties of managing mixed waste that contains high-activity radioactive materials, and the physical limitations of working remotely in the areas within the subject …
Date:
March 25, 1998
Creator:
Barnett, J. M.
System:
The UNT Digital Library
324 Building special-case waste assessment in support of the 324 Building closure (TPA milestone M-89-05)
Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement Milestone M-89-05 requires US Department of Energy, Richland Operations Office to complete a 324 Building Special Case Waste Assessment in Support of the 324 Building Closure. This document has been prepared with the intent of meeting this regulatory commitment. Alternatives for the Special Case Wastes located in the 324 Building were defined and analyzed. Based on the criteria of safety, environmental, complexity of interfaces, risk, cost, schedule, and long-term operability and maintainability, the best alternative was chosen. Waste packaging and transportation options are also included in the recommendations. The waste disposition recommendations for the B-Cell dispersibles/tank heels and High-Level Vault packaged residuals are to direct them to the Plutonium Uranium Extraction Facility (PUREX) Number 2 storage tunnel.
Date:
May 12, 1998
Creator:
Hobart, R.L.
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 4.
Date:
October 27, 1998
Creator:
Carlson, J. L.
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 5B.
Date:
November 24, 1998
Creator:
RIDDELLE, J.G.
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 5a.
Date:
October 27, 1998
Creator:
RIDDELLE, J.G.
System:
The UNT Digital Library
324 Facility B-Cell quality process plan
This report documents the quality process plan for the restart of a hot cell in the B Plant, originally a bismuth phosphate processing facility, but later converted to a waste fractionation plant. B-Cell is currently being cleaned out and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/1999. This report describes the major activities that remain for completion of the TPA milestone.
Date:
March 12, 1998
Creator:
Carlson, J. L.
System:
The UNT Digital Library
324 Facility B-cell quality process plan
B-Cell is currently being cleaned out (i.e., removal of equipment, fixtures and residual radioactive materials) and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/99. The following sections describe the major activities that remain for completion of the TPA milestone. These include: Size Reduce Tank 119 and Miscellaneous Equipment; Load and Ship Low-Level Waste; Remove and Size Reduce the 1B Rack; Collect Dispersible Material from Cell Floor; Remove and Size Reduce the 2A Rack; Size Reduce the 1A Rack; Load and Ship Mixed Waste to PUREX Tunnels; and Move Spent Fuel to A-Cell;
Date:
July 29, 1998
Creator:
Carlson, J.L.
System:
The UNT Digital Library
324 Facility B-Cell quality process plan
B-Cell is currently being cleaned out (i.e., removal of equipment, fixtures and residual radioactive materials) and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/99. The following sections describe the major activities that remain for completion of the TPA milestone. These include: Size Reduce Tank 119 and Miscellaneous Equipment; Load and Ship Low-Level Waste; Remove and Size Reduce the 1B Rack; Collect Dispersible Material from Cell Floor; Remove and Size Reduce the 2A Rack; Size Reduce the 1A Rack; Load and Ship Mixed Waste to PUREX Tunnels; and Move Spent Fuel to A-Cell;
Date:
April 29, 1998
Creator:
Carlson, J.L.
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 6a.
Date:
November 24, 1998
Creator:
RIDDELLE, J.G.
System:
The UNT Digital Library