60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017 (open access)

60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017

This report presents the details of the auger sampling events for underground waste tank C-111. The samples were shipped to the 222-S laboratories were they underwent safety screening analysis and primary ferricyanide analysis. The samples were analyzed for alpha total, total organic carbon, cyanide, Ni, moisture, and temperature differentials. The results of this analysis are presented in this document.
Date: May 30, 1995
Creator: Rice, A.D.
Object Type: Report
System: The UNT Digital Library
Acceptance test procedure for High Pressure Water Jet System (open access)

Acceptance test procedure for High Pressure Water Jet System

The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet.
Date: May 30, 1995
Creator: Crystal, J.B.
Object Type: Report
System: The UNT Digital Library
Acceptance Test Procedure: SY101 air pallet system (open access)

Acceptance Test Procedure: SY101 air pallet system

The purpose of this test procedure is to verify that the system(s) procured to load the SY-101 Mitigation Test Pump package fulfills its functional requirements. It will also help determine the man dose expected due to handling of the package during the actual event. The scope of this procedure focuses on the ability of the air pallets and container saddles to carry the container package from the new 100 foot concrete pad into 2403-WD where it will be stored awaiting final disposition. This test attempts to simulate the actual event of depositing the SY-101 hydrogen mitigation test pump into the 2403-WD building. However, at the time of testing road modifications required to drive the 100 ton trailer into CWC were not performed. Therefore a flatbed trailer will be use to transport the container to CWC. The time required to off load the container from the 100 ton trailer will be recorded for man dose evaluation on location. The cranes used for this test will also be different than the actual event. This is not considered to be an issue due to minimal effects on man dose.
Date: May 30, 1995
Creator: Koons, B.M.
Object Type: Report
System: The UNT Digital Library
Advanced secondary recovery demonstration for the Sooner Unit. Progress report, July 1--September 30, 1995 (open access)

Advanced secondary recovery demonstration for the Sooner Unit. Progress report, July 1--September 30, 1995

The objective of this project is to increase production from the Cretaceous ``D`` Sand in the Denver-Julesburg (D-J) Basin through geologically targeted infill drilling and improved reservoir management of waterflood operations. This project involves multi-disciplinary reservoir characterization using high-density 3-D seismic, detailed stratigraphy and reservoir simulation studies. Infill drilling, water-injection conversion and recompleting some wells to add short-radius laterals will be based on the results of the reservoir characterization studies. Production response will be evaluated using reservoir simulation and production tests. Technology transfer will utilize workshops, presentations and technical papers which will emphasize the economic advantages of implementing the demonstrated technologies. The success of this project and effective technology transfer should prompt-re-appraisal of older waterflood projects and implementation of new projects in oil provinces such as the D-J Basin. Three wells have been drilled by the project based on 3-D seismic and integrated reservoir characterization study. Oil production has increased in September to 54.0 m{sup 3}/D (340 bopd) after the completion of the SU 21-16-9. Combination-attribute maps from 3-D seismic data closely predicted the net-pay thickness of the new well. Inter-well tracer tests with sodium bromide indicate a high-permeability channel between two wells. An oral presentation was made at the …
Date: September 30, 1995
Creator: Sippel, M.A. & Cammon, T.J.
Object Type: Report
System: The UNT Digital Library
Los Alamos National Laboratory 1995 self assessment report (open access)

Los Alamos National Laboratory 1995 self assessment report

The Los Alamos National Laboratory (LANL) Safeguards and Security (S and S) Assurance Program (AP) is designed to ensure the adequacy and effectiveness of the LANL S and S program. The Assurance Program provides a mechanism for discovering deficiencies, determining causes, conducting risk assessments, implementing corrective actions, and documenting the assessment process. Selection of organizations for self assessments is based on the criteria established in the LANL S and S Assurance Program. For FY 1995, 12 organizations were selected for self assessments, these organizations are identified fin the schedule at Appendix A. The S and S topical areas selected for review in each organization varied depending on their security interests and included: Program Planning and Management (PPM); Protection Program Operations (PPO); Material Control and Accountability (MC and A); Computer and Communications Security (COMPSEC and COMSEC); Information Security (INFOSEC); Personnel Security (PERSEC); and Operational Security (OPSEC). The objective was to ascertain the effectiveness of S and S programs in each organization, its formality of operations, and its integration with the overall Laboratory S and S program. The goal was to meet both the DOE self-assessment requirements and the UC performance criteria and document the results.
Date: June 30, 1995
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Los Alamos National Laboratory Facilities, Security and Safeguards Division, Safeguards and Security Program Office, Protective Force Oversight Program (open access)

Los Alamos National Laboratory Facilities, Security and Safeguards Division, Safeguards and Security Program Office, Protective Force Oversight Program

The purpose of this document is to identify and describe the duties and responsibilities of Facility Security and Safeguards (FSS) Safeguards and Security (SS) organizations (groups/offices) with oversight functions over the Protection Force (PF) subcontractor. Responsible organizations will continue their present PF oversight functions under the Cost Plus Award Fee (CPAF) assessment, but now will be required to also coordinate, integrate, and interface with other FSS S and S organizations and with the PF subcontractor to measure performance, assess Department of Energy (DOE) compliance, reduce costs, and minimize duplication of effort. The role of the PF subcontractor is to provide the Laboratory with effective and efficient protective force services. PF services include providing protection for the special nuclear material, government property and classified or sensitive information developed and/or consigned to the Laboratory, as well as protection for personnel who work or participate in laboratory activities. FSS S and S oversight of both performance and compliance standards/metrics is essential for these PF objectives to be met.
Date: November 30, 1995
Creator: unknown
Object Type: Report
System: The UNT Digital Library
[Alternative fuel vehicles for clean cities]. Final report from the City of Philadelphia Managing Director`s Office (open access)

[Alternative fuel vehicles for clean cities]. Final report from the City of Philadelphia Managing Director`s Office

The City of Philadelphia was awarded a grant for the ``development of a Public Information Component for the Clean Cities Program involving alternative fuels usage within the city of Philadelphia and the surrounding counties in the Philadelphia region``. During the summer of 1993, it was felt that the public needed considerable information on the costs, benefits, emission data, conversion information, and infrastructure requirements. Embodied in the 1993 proposal was the notion that a model could be developed within some type of structure charged with the tasks of market introduction of alternative fuels in the Greater Philadelphia area in a concerted, comprehensive way. As originally envisioned, in executing this grant, the City had several objectives in mind. Among these were the following: the organizing of various media events to showcase alternative fuels usage; (2) to begin a networking process with fleet managers in the area; (3) to provide sources of information to fleet managers and others interested in, and concerned with the conversion to alternative fuels; (4) documentation on research and analysis associated with alternative fuels.
Date: September 30, 1995
Creator: Hadalski, J.M.
Object Type: Report
System: The UNT Digital Library
Alternative Technical Summary Report: Electrometallurgical Treatment Variant (open access)

Alternative Technical Summary Report: Electrometallurgical Treatment Variant

Immobilization is the fixation of the surplus fissile materials in an acceptable matrix such as glass or ceramics to create an environmentally benign form for disposal in a repository. In addition to the traditional characteristics required of an immobilization form to achieve isolation of the fissile material from the biosphere over geologic times, the immobilization form for the Fissile Materials Disposition Program (FMDP) must also possess the property that it is inherently as unattractive and inaccessible as the fissile material from commercial spent fuel. This latter requirement is similar to the wording of the ''spent fuel standard'' invoked in the National Academy of Sciences (NAS) study on plutonium disposition. High-level wastes (HLW) or separated cesium ({sup 137}Cs), can be added with the fissile material into the waste form to create a radiation field that increases the proliferation resistance and decreases reuse by the host nation in the following ways: (1) Plutonium will be diluted with elements that must be removed by extensive chemical processing to return it to weapons-usable purity; (2) The immobilized plutonium canisters will contain approximately 2 tonnes (2000 kg; 2.2 tons) of mass, thereby forcing the use of heavy equipment to move the canisters; (3) A gamma …
Date: November 30, 1995
Creator: Gray, L.W.
Object Type: Report
System: The UNT Digital Library
Application of advanced reservoir characterization, simulation, and production optimization strategies to maximize recovery in slope and basin clastic reservoirs, West Texas. Technical progress report, April 1--June 30, 1995 (open access)

Application of advanced reservoir characterization, simulation, and production optimization strategies to maximize recovery in slope and basin clastic reservoirs, West Texas. Technical progress report, April 1--June 30, 1995

The objective of this project is to demonstrate that detailed reservoir characterization of slope and basin clastic reservoirs in sandstones of the Delaware Mountain Group in the Delaware Basin of West Texas and New mexico is a cost-effective way to recover a higher percentage of the original oil in place through strategic placement of infill wells and geologically based field development. Project objectives are divided into two major phases. The objectives of the reservoir characterization phase of the project are to provide a detailed understanding of the architecture and heterogeneity of two fields, the Ford Geraldine Unit and Ford West field, which produce from the Bell Canyon and Cherry Canyon Formations, respectively, of the Delaware Mountain Group and to compare Bell Canyon and Cherry Canyon reservoirs. Reservoir characterization will utilize 3-D seismic data, high-resolution sequence stratigraphy, subsurface field studies, outcrop characterization, and other techniques. Once the reservoir characterization study of both fields is completed, a pilot area of approximately 1 mi{sup 2} in one of the fields will be chosen for reservoir simulation. The objectives of the implementation phase of the project are to (1) apply the knowledge gained from reservoir characterization and simulation studies to increase recovery from the …
Date: June 30, 1995
Creator: Dutton, S. P.
Object Type: Report
System: The UNT Digital Library
Application of Municipal Sewage Sludge to Forest and Degraded Land (open access)

Application of Municipal Sewage Sludge to Forest and Degraded Land

The paper summarizes research done over a decade at the Savannah River Site and elsewhere in the South evaluating the benefits of land application of municipal wastes. Studies have demonstrated that degraded lands, ranging from borrow pits to mine spoils can be successfully revegetated using a mixture of composed municipal sewage sludge and other amendments. The studies have demonstrated a practical approach to land application and restoration.
Date: September 30, 1995
Creator: Marx, D. H.; Berry, C. R. & Kormanik, P. P.
Object Type: Article
System: The UNT Digital Library
Assist in the Recovery of Bypassed Oil From Reservoirs in the Gulf of Mexico. Quarterly Report, April 1, 1995--June 31, 1995 (open access)

Assist in the Recovery of Bypassed Oil From Reservoirs in the Gulf of Mexico. Quarterly Report, April 1, 1995--June 31, 1995

Objective is to assist the recovery of remaining noncontacted oil from known reservoirs/abandoned offshore wells on the Outer Continental Shelf in the Gulf of Mexico. Progress continues for reducing the data to fit a simplified model and redescribing the resource to accommodate known production behavior and geologic assumptions. Final reports are currently being prepared.
Date: July 30, 1995
Creator: Schenewerk, P. A.
Object Type: Report
System: The UNT Digital Library
Assistance to the states with risk based data management. Quarterly technical progress report, July 1--September 30, 1995 (open access)

Assistance to the states with risk based data management. Quarterly technical progress report, July 1--September 30, 1995

The Tasks of this project are to: Task 1--complete implementation of a Risk Based Data Management System (RBDMS) in the states of Alaska, Mississippi, Montana, and Nebraska; and Task 2--conduct Area of Review (AOR) workshops in the states of California, Oklahoma, Kansas, and Texas. In general, Task 1 provides assistance to the named states with converting data from existing data management systems where applicable; coding and internal testing of the RBDMS; preparing documentation, training, and technology transfer; plus project management. Development of RBDMS in the first grouping of states (AK, MS, MT, and NB) is complete. The paper describes the RBDMS features, continued implementation of the RBDMS and future RBDMS workshops. RBDMS includes comprehensive well information for both producing and injection well types. The purpose of AOR workshops is to acquaint state agency and industry personnel with the AOR variance methodology that has been developed and to seek input from the attendees concerning application of variance methods to injection fields in the state. Workshops have been successfully completed in California and Oklahoma. The Kansas and Texas workshops are tentatively scheduled to take place in November.
Date: October 30, 1995
Creator: Paque, M. J.
Object Type: Report
System: The UNT Digital Library
Celebrating success at Fernald (open access)

Celebrating success at Fernald

Restoration of the Fernald Environmental Management Project is now moving from the environmental investigation stage to real, tangible remediation progress. Using a variety of programmatic innovations, DOE and FERMCO continue to strengthen an effective partnership that supports a mutually-developed mission of safe, least-cost, earliest final remediation of the Fernald Site while complying with all applicable DOE Orders, regulatory requirements and commitments and addressing the concerns of the many stakeholders who have an interest in how remediation at Fernald progresses. The progress that is occurring at Fernald is testimony to a productive DOE/FERMCO partnership that will continue to be an essential part of the difficult environmental restoration task at this site.
Date: January 30, 1995
Creator: Ofte, D.; Baublitz, J. E.; Chaney, K. & Hansen, R.
Object Type: Article
System: The UNT Digital Library
Chemical and nuclear properties of Rutherfordium (Element 104) (open access)

Chemical and nuclear properties of Rutherfordium (Element 104)

The chemical-properties of rutherfordium (Rf) and its group 4 homologs were studied by sorption on glass support surfaces coated with cobalt(II)ferrocyanide and by solvent extraction with tributylphosphate (TBP) and triisooctylamine (TIOA). The surface studies showed that the hydrolysis trend in the group 4 elements and the pseudogroup 4 element, lb, decreases in the order Rf>Zr{approx}Hf>Th. This trend was attributed to relativistic effects which predicted that Rf would be more prone to having a coordination number of 6 than 8 in most aqueous solutions due to a destabilization of the 6d{sub 5/2} shell and a stabilization of the 7p{sub l/2} shell. This hydrolysis trend was confirmed in the TBP/HBr solvent extraction studies which showed that the extraction trend decreased in the order Zr>Hf>Rf?Ti for HBr, showing that Rf and Ti did not extract as well because they hydrolyzed more easily than Zr and Hf. The TIOA/HF solvent extraction studies showed that the extraction trend for the group 4 elements decreased in the order Ti>Zr{approx}Hf>Rf, in inverse order from the trend of ionic radii Rf>Zr{approx}Hf>Ti. An attempt was made to produce {sup 263}Rf (a) via the {sup 248}Cm({sup 22}Ne, {alpha}3n) reaction employing thenoyltrifluoroacetone (TTA) solvent extraction chemistry and (b) via the {sup …
Date: October 30, 1995
Creator: Kacher, C. D.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Co-firing high sulfur coal with refuse derived fuels. Technical progress report No. 5, [October--December 1995] (open access)

Co-firing high sulfur coal with refuse derived fuels. Technical progress report No. 5, [October--December 1995]

Studies involving the tubular furnace are in the process of identifying the ideal experimental coal-to-refuse derived fuel(RDF) ratio for use in the AFBC system. A series of experiments with this furnace has been performed to determine the possible chemical pathway for formation of chlorinated organic compounds during the combustion of various RDF sources. Phenol and chlorine appear to be likely reactants necessary for the formation of these compounds. The main goal of these experiment is to determine the exact experimental conditions for the formation of chlorinated organic compounds, as well as methods to inhibit their development. Work on the fluidized bed combustor has involved five combustion runs, in which a combustion efficiency of greater than 96% and with a consistent CO{sub 2} concentration of approximately 13% was obtained. Modifications responsible for these improvements include the addition of the underbed fuel feed system and revision of the flue gas sampling system. New methods of determining combustion efficiency and percentage of SO{sub 2} capture using TG techniques to analyze combustion products are being developed. The current outlook using this TGA/FTIR method is very promising, since previously obscured reactions are being studied. the analysis of combustion products is revealing a more complete picture …
Date: November 30, 1995
Creator: Pan, Wei-Ping; Riley, J. T. & Lloyd, W. G.
Object Type: Report
System: The UNT Digital Library
Combustion characterization of carbonized RDF, Joint Venture Task No. 7. Topical Report (open access)

Combustion characterization of carbonized RDF, Joint Venture Task No. 7. Topical Report

The overall objective of this research program was to demonstrate EnerTech�s and the Energy & Environmental Research Center�s (EERC) process of slurry carbonization for producing homogeneous, pumpable titels from refuse-derived fuel (RDF) with continuous pilot plant facilities, and to characterize flue gas and ash emissions from combustion of the carbonizd RDF slurry fuel. Please note that �Wet Thermal Oxidation� is EnerTech�s trademark mme for combustion of the carbonized RDF slurry fuel. Carbonized RDF slurry fuels were produced with the EERC�S 7.5-tpd (wet basis) pilot plant facility. A hose diaphragm pump pressurized a 7- lo-wt% feed RDF slurry, with a viscosity of 500 cP, to approximately 2500 psig. The pressurized RDF slurry was heated by indirect heat exchangers to between 5850 -626�F, and its temperature and pressure was maintained in a downflow reactor. The carbonized slurry was flashed, concentrated in a filter press, and ground in an attritor. During operation of the pilot plant, samples of the feed RDF slurry, carbonization gas, condensate, carbonized solids, and filtrate were taken and analyzed. Pilot-scale slurry carbonization experiments with RDF produced a homogeneous pumpable slurry fuel with a higher heating value (HHV) of 3,000-6,600 Btu/lb (as-received basis), at a viscosity of 500 CP at …
Date: April 30, 1995
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Comparison between predicted and actual accuracies for an Ultra-Precision CNC measuring machine (open access)

Comparison between predicted and actual accuracies for an Ultra-Precision CNC measuring machine

At the 1989 CIRP annual meeting, we reported on the design of a specialized, ultra-precision CNC measuring machine, and on the error budget that was developed to guide the design process. In our paper we proposed a combinatorial rule for merging estimated and/or calculated values for all known sources of error, to yield a single overall predicted accuracy for the machine. In this paper we compare our original predictions with measured performance of the completed instrument.
Date: May 30, 1995
Creator: Thompson, D.C. & Fix, B.L.
Object Type: Article
System: The UNT Digital Library
Conceptual Decontamination and Decommissioning Plan for the Waste Isolation Pilot Plant (open access)

Conceptual Decontamination and Decommissioning Plan for the Waste Isolation Pilot Plant

The Conceptual Decontamination and Decommissioning Plan (D&D) was developed as a concept for progressing from the final actions of the Disposal Phase, through the Decontamination and Decommissioning Phase, and into the initiation of the Long-Term Monitoring Phase. This plan was written in a manner that coincides with many of the requirements specified in DOE Order 5820.2A. Radioactive Waste Management; ASTM El 167 87, Standard Guide for Radiation Protection Program for Decommissioning Operations; and other documents listed in Attachment 3 of the D&D Plan. However, this conceptual plan does not meet all of the requirements necessary for a Decontamination and Decommissioning plan necessary for submission to the U.S. Congress in accordance with the Land Withdrawal Act (P.L. 102-579). A complete D&D plan that will meet the requirements of all of these documents and of the Land Withdrawal Act will be prepared and submitted to Congress by October 1997.
Date: January 30, 1995
Creator: Westinghouse Electric Corporation Waste Isolation Division, now Washington TRU Solutions LLC
Object Type: Report
System: The UNT Digital Library
Considerations on the performance and fabrication of candidate materials for the Yucca Mountain repository waste packages highly corrosion resistant nickel-base and titanium-base alloys (open access)

Considerations on the performance and fabrication of candidate materials for the Yucca Mountain repository waste packages highly corrosion resistant nickel-base and titanium-base alloys

Among the metallurgical factors that affect the performance of a material in a given environment are alloy composition, alloy segregation, depletion of alloying elements, non-uniform microstructures, precipitation leading to an increase in susceptibility to corrosion as well as decreases in ductility, residual plastic deformation, and residual stresses. Precipitation often occurs preferentially at grain boundaries, causing depletion of critical elements in regions adjacent to these boundaries. Continuous grain-boundary precipitates can lead to drops in ductility and toughness. The presence of non-metallic inclusions, if excessive and/or segregated, can also cause embrittlement. Segregation of alloying elements can result in localized galvanic action. Depletion of alloying elements as well as segregation can result in reductions in the concentrations of critical elements below those necessary to resist localized corrosion. Segregation and alloy depletion can also facilitate precipitation that could lead to embrittlement.
Date: November 30, 1995
Creator: Dalder, E & Goldberg, A
Object Type: Report
System: The UNT Digital Library
Degradation mode survey of titanium-base alloys (open access)

Degradation mode survey of titanium-base alloys

Of the materials reviewed, commercially pure titanium, Ti Gr 2, is the most susceptible to crevice corrosion. Ti Gr 7, 12, and 16 are likely to be resistant to crevice corrosion under the current expected Yucca Mountain repository conditions. Although Grade 7 has the greatest resistance to crevice corrosion it is also the most expensive. Although the possibility of sustained loads cracking exists, it has not yet been observed in a Ti alloys. For hydride precipitation to occur 100{degrees}C, the hydrogen concentration would need to be relatively high, much higher than the maximum amount of hydrogen allowed during the manufacture of ({alpha} Ti alloys (0.0 15 wt%). A large amount of (SCC) stress corrosion cracking data accumulated at SNL and BNL for the WIPP program and by the Canadian Waste Management Program on titanium grades 2 and 12 indicates that there is no SCC at naturally occurring potentials in various brines. Hydride-induced cracking of titanium is a possibility and therefore, further investigation of this phenomenon under credible repository conditions is warranted. One disadvantage of titanium and its alloys is that their strengths decrease rather rapidly with temperature. This is due to the strong temperature dependence of interstitial solute strengthening mechanisms. …
Date: January 30, 1995
Creator: Gdowski, G. E. & Ahluwalia, H. S.
Object Type: Report
System: The UNT Digital Library
Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1 (open access)

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 1

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation. These Appendices contain the Federal Register Notice, comments on evaluation factors, independent technical reviewers resumes, independent technical reviewers manual, …
Date: June 30, 1995
Creator: Zoller, J. N.; Rosen, R. S. & Holliday, M. A.
Object Type: Report
System: The UNT Digital Library
Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2 (open access)

Depleted Uranium Hexafluoride Management Program. The technology assessment report for the long-term management of depleted uranium hexafluoride. Volume 2

With the publication of a Request for Recommendations and Advance Notice of Intent in the November 10, 1994 Federal Register, the Department of Energy initiated a program to assess alternative strategies for the long-term management or use of depleted uranium hexafluoride. This Request was made to help ensure that, by seeking as many recommendations as possible, Department management considers reasonable options in the long-range management strategy. The Depleted Uranium Hexafluoride Management Program consists of three major program elements: Engineering Analysis, Cost Analysis, and an Environmental Impact Statement. This Technology Assessment Report is the first part of the Engineering Analysis Project, and assesses recommendations from interested persons, industry, and Government agencies for potential uses for the depleted uranium hexafluoride stored at the gaseous diffusion plants in Paducah, Kentucky, and Portsmouth, Ohio, and at the Oak Ridge Reservation in Tennessee. Technologies that could facilitate the long-term management of this material are also assessed. The purpose of the Technology Assessment Report is to present the results of the evaluation of these recommendations. Department management will decide which recommendations will receive further study and evaluation.
Date: June 30, 1995
Creator: Zoller, J. N.; Rosen, R. S. & Holliday, M. A.
Object Type: Report
System: The UNT Digital Library
Development of a membrane-based process for the treatment of oily waste waters. Annual report, March 4, 1993--March 5, 1995 (open access)

Development of a membrane-based process for the treatment of oily waste waters. Annual report, March 4, 1993--March 5, 1995

The goal of this program was to develop an economical oily-water treatment system based on reverse-osmosis (RO) membrane technology. The RO system would be used to: (1) reduce oil-production costs by reducing the volume of waste water for which disposal is required; (2) form the basis of a generic waste-water treatment system that can easily be integrated into oil-field operations, especially at production facilities that are small or in remote locations: and (3) produce water clean enough to meet current and anticipated environmental regulations. The specific focus of this program was to develop a hollow-fiber membrane module capable of treating oily waste waters. Typically, the organics in oily waste water swell or dissolve the materials used in conventional polymeric membranes and modules. Our goal was to develop hollow-fiber membranes and modules that were more solvent-resistant than conventional membrane modules. We successfully achieved this goal. During the course of this program. we developed thin-film-composite (TFC) membranes, which consisted of a solvent-resistant selective coating placed on a solvent-resistant hollow-fiber support. These TFC membranes were used in low-cost, hollow-fiber modules, which were made using solvent-resistant components. The modules were tube-side-feed modules, in which the oily waste water travels down the inside (lumen) of …
Date: August 30, 1995
Creator: McCray, S.B.
Object Type: Report
System: The UNT Digital Library
Development of a metal ceramic composite crucible. Final CRADA report for CRADA number Y-1292-0079 (open access)

Development of a metal ceramic composite crucible. Final CRADA report for CRADA number Y-1292-0079

This Cooperative Research and Development Agreement (CRADA) has been a three-year collaboration among the Y-12 Plant Development Division, Blasch Precision Ceramics, Inc., and Surface Alloys, Inc. The purpose of the CRADA was to evaluate the production of a totally new crucible that would be noncarbon and that could perform like graphite. The effort required materials fabricated into a workable crucible. The goal was to produce a crucible that could be induction heated and allow melting of reactive metals without appreciable carbon contamination. The US Department of Energy programs involving casting uranium and its alloys have long been concerned with reducing deleterious carbon pickup that results from the use of graphite crucibles. Therefore, the results of this CRADA provide an alternative that can eliminate carbon pickup from the graphite crucible.
Date: September 30, 1995
Creator: Morrow, M. S.; Holcombe, C. E., Jr.; Kiggans, J. O., Jr.; Rexford, D. & Rausch, J. J.
Object Type: Report
System: The UNT Digital Library