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5,057 Matching Results
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Controlled Design Assumptions Document
The objective of the Controlled Design Assumptions Document (CDA) is to provide documentation and control of Mined Geologic Disposal System (MGDS) design assumptions in support of design and performance assessment in preparing for the Viability Assessment (VA).
Date:
September 12, 1996
Creator:
United States. Department of Energy.
Object Type:
Report
System:
The UNT Digital Library
Assessment of industrial minerals and rocks in the controlled area
Yucca Mountain in Nye County, Nevada, is a potential site for a permanent repository for high-level nuclear waste in Miocene ash flow tuff. The Yucca Mountain controlled area occupies approximately 98 km{sup 2} that includes the potential repository site. The Yucca Mountain controlled area is located within the southwestern Nevada volcanic field, a large area of Miocene volcanism that includes at least four major calderas or cauldrons. It is sited on a remnant of a Neogene volcanic plateau that was centered around the Timber Mountain caldera complex. The Yucca Mountain region contains many occurrences of valuable or potentially valuable industrial minerals, including deposits with past or current production of construction aggregate, borate minerals, clay, building stone, fluorspar, silicate, and zeolites. The existence of these deposits in the region and the occurrence of certain mineral materials at Yucca Mountain, indicate that the controlled area may have potential for industrial mineral and rock deposits. Consideration of the industrial mineral potential within the Yucca Mountain controlled area is mainly based on petrographic and lithologic studies of samples from drill holes in Yucca Mountain. Clay minerals, zeolites, fluorite, and barite, as minerals that are produced economically in Nevada, have been identified in samples from …
Date:
August 1, 1996
Creator:
Castor, S. B. & Lock, D. E.
Object Type:
Report
System:
The UNT Digital Library
Controlled, clean, and stable design requirements document for single-shell tank farms
The Controlled, Clean, and Stable (CCS) Design Requirements Document (DRD) contains the technically defensible and traceable functions and requirements for maintaining the Single-Shell Tank Farms in a cost effective and safe interim end state. The CCSDRD functions and requirements constitute the project characteristics that are minimally sufficient to meet the CCS mission goals.
Date:
June 19, 1996
Creator:
Vanderzanden, M.D., Westinghouse Hanford
Object Type:
Report
System:
The UNT Digital Library
Optics and materials research for controlled radiant energy transfer in buildings. Final technical report
The primary objective of this project was to perform the optics and materials research necessary to identify and solve the technical problems associated with fabricating durable, variable reflectivity electrochromic windows for energy efficient buildings and vehicles. The research performed at the Tufts Electro-Optics Technology Center (EOTC) has identified and solved nearly all the significant problems, as discussed below in this final technical report. There still remains, however, one important problem to be solved--i.e., to better understand the science of deposition processes and thereby develop and optimize one or more production-worthy deposition processes that could be used for the practical production of affordable, variable reflectivity electrochromic windows. Therefore, it is recommended that such studies be carried out with the goals of: (1) determining the probable practical limits of performance; and, very importantly, (2) to develop and optimize deposition processes that could be used for the practical production of affordable electrochromic windows.
Date:
July 1, 1996
Creator:
Goldner, R.B.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of pressure response in the Los Alamos controlled air incinerator during three incident scenarios
The Los Alamos Controlled Air Incinerator (CAI) is a system designed to accept radioactive mixed waste containing alpha-emitting radionuclides. A mathematical model was developed to predict the pressure response throughout the offgas treatment system of the CAI during three hypothetical incident scenarios. The scenarios examined included: (1) loss of burner flame and failure of the flame safeguard system with subsequent reignition of fuel gas in the primary chamber, (2) pyrolytic gas buildup from a waste package due to loss of induced draft and subsequent restoration of induced draft, and (3) accidental charging of propellant spray cans in a solid waste package to the primary chamber during a normal feed cycle. For each of the three scenarios, the finite element computer model was able to determine the transient pressure surge and decay response throughout the system. Of particular interest were the maximum absolute pressures attainable at critical points in the system as well as maximum differential pressures across the high efficiency particulate air (HEPA) filters. Modeling results indicated that all three of the scenarios resulted in maximum HEPA filter differential pressures well below the maximum allowable levels.
Date:
May 1, 1996
Creator:
Vavruska, John S.; Elsberry, Kathy; Thompson, T. K. & Pendergrass, John A.
Object Type:
Article
System:
The UNT Digital Library
Magnetically controlled deposition of metals using gas plasma. Quarterly progress report, July--September 1996
Objective is to develop a method of spraying materials on a substrate in a controlled manner to eliminate the waste inherent in present plating processes. The process under investigation is magnetically controlled plasma spraying. The field equations have been cast in a format that allows finite element solution. Potential flow and finite element solutions for temperature isolines and velocity vectors are compared for 2-D flow with heat addition.
Date:
November 1, 1996
Creator:
Woodall, D.M. & Lemmon, E.C.
Object Type:
Report
System:
The UNT Digital Library
Safety criteria for organic watch list tanks at the Hanford Site
This document reviews the hazards associated with the storage of organic complexant salts in Hanford Site high-level waste single- shell tanks. The results of this analysis were used to categorize tank wastes as safe, unconditionally safe, or unsafe. Sufficient data were available to categorize 67 tanks; 63 tanks were categorized as safe, and four tanks were categorized as conditionally safe. No tanks were categorized as unsafe. The remaining 82 SSTs lack sufficient data to be categorized.Historic tank data and an analysis of variance model were used to prioritize the remaining tanks for characterization.
Date:
August 1, 1996
Creator:
Meacham, J. E.
Object Type:
Report
System:
The UNT Digital Library
Tank waste remediations system controlled, clean, and stable functions and endpoint criteria for single-shell tank farms
This document provides functions and endpoint criteria to be used for transition of the Single-Shell Tank Farms to the Controlled, Clean and Stable endstate.
Date:
February 6, 1996
Creator:
Hull, K.J.
Object Type:
Report
System:
The UNT Digital Library
Title list of documents made publicly available, November 1-30, 1995
The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docker Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical …
Date:
January 1, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Safeguards summary event list (SSEL), January 1, 1990--December 31, 1995
The Safeguards Summary Event List (SSEL), Vol. 2, Rev. 4, provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC) which occurred and were reported from January 1, 1990, rough December 31, 1995. Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of Bomb-related, Intrusion, Missing and/or Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms, Radiological Sabotage, Nonradiological Sabotage, and Miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels.
Date:
July 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Interim safety equipment list for 241-C-106 waste retrieval, project W-320
The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry distributor in tank 241-AY-102; heating, ventilation, and air conditioning for tank 241-C-106; and instrumentation and control devices.
Date:
January 25, 1996
Creator:
Conner, J. C.
Object Type:
Report
System:
The UNT Digital Library
Test report of evaluation of primary exhaust ventilation flowmeters for double shell hydrogen watch list tanks
This document reports the results of testing four different flowmeters for use in the primary exhaust ventilation ducts of Double Shell Tanks on the hydrogen watch list that do not already have this capability. This currently includes tanks 241-AW-101,241-AN- 103, 241-AN-104, 241-AN-105 and 241-SY-103. The anticipated airflow velocity in these tanks range from 0.25 m/s(50 ft/min) to 1/78 m/s (350 ft/min). Past experiences at Hanford have forced the evaluation and selection of instruments to be used at the low flow and relatively high humidity conditions found in these tanks. Based on the results of this test, a flow meter has been chosen for installation in the primary exhaust ventilation ducts of the above mentioned waste tanks.
Date:
September 3, 1996
Creator:
Willingham, W.E., Westinghouse Hanford
Object Type:
Report
System:
The UNT Digital Library
DOE technical standards list: Directory of DOE and contractor personnel involved in non-government standards activities
The body of this document contains a listing of DOE employees and DOE contractors who have submitted form DOE F 1300.2, Record of Non-Government Standards Activity, which is attached to the end of this document and to DOE Order 1300.2A. Additional names were added from rosters supplied by non-Government standards bodies. The committees or governing bodies in which the person participates is listed after each name. An asterisk preceding the committee notation indicates that the person has identified himself or herself as the DOE representative on that committee. Appendices to this document are also provided to sort the information by the parent employment organization, by non-Government standards activity, and by the proper names of the non-Government standards organizations and committees. DOE employees and contractors listed in this TSL are those recorded as of July 1, 1996.
Date:
August 1, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Test plan for evaluation of primary exhaust ventilation flow meters for double shell hydrogen watch list tanks
This document is a plan for testing four different flow meters for use in the primary exhaust ventilation ducts of Double Shell Tanks on the hydrogen watch list that do not already have this capability. This currently includes tanks 241-AW-101, 241-AN-103, 241-AN-104, 241-AN-105, and 241-SY-103. The anticipated airflow velocity in these tanks range from 0.25 m/s(50 ft/min) to 1.78 m/s (350 ft/min). Past experiences at Hanford are forcing the evaluation and selection of instruments to be used at the low flow and relatively high humidity conditions found in these tanks. Based on the results of this test, a flow meter shall be chosen for installation in the primary exhaust ventilation ducts of the above mentioned waste tanks.
Date:
May 2, 1996
Creator:
Willingham, W.E.
Object Type:
Report
System:
The UNT Digital Library
Particulate behavior in a controlled-profile pulverized coal-fired reactor: A study of coupled turbulent particle dispersion and thermal radiation transport. Final technical progress report
To aid in the evaluation and development of advanced coal-combustion models, comprehensive experimental data sets are needed containing information on both the condensed and gas phases. To address this need a series of test were initiated on a 300 kW laboratory-scale, coal-fired reactor at a single test condition using several types of instrumentation. Data collected on the reactor during the course of the test includes: gas, particle, and wall temperature profiles; radiant, total, and convective heat fluxes to the walls; particle size and velocity profiles; transmission measurements; and gas species concentrations. Solid sampling was also performed to determine carbon and total burnout. Along with the extensive experimental measurements, the particle dispersion and radiation submodels in the ACERC comprehensive 2D code were studied in detail and compared to past experimental measurements taken in the CPR. In addition to the presentation and discussion of the experimental data set, a detailed description of the measurement techniques used in collecting the data, including a discussion of the error associated with each type of measurement, is given.
Date:
June 1, 1996
Creator:
Queiroz, M. & Webb, B.W.
Object Type:
Report
System:
The UNT Digital Library
Title list of documents made publicly available, July 1--31, 1996: Volume 18, No. 7
This monthly publication describes information received and published by US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. Following indexes are included: personal author, corporate source, report number, and cross reference of enclosures to principal documents.
Date:
September 1, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4
This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.
Date:
June 1, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Decontamination and decommissioning of rooms 62-248 and 62-250 at Ernest Orlando Lawrence Berkeley National Laboratory
This document details the decontamination and decommissioning (D&D) process of Rooms 248 and 250 of Building 62 at the Ernest Orlando Lawrence Berkeley National Laboratory (LBNL). The document describes the D&D efforts for the rooms, their contents, and adjacent areas containing ancillary equipment. The rooms and equipment, before being released, were required to meet the unrestricted release criteria and requirements set forth in DOE orders 5400.5 and 5480.11, LBNL`s internal release-criteria procedure (EH&S Procedure 708), and the LBNL Radiological Control Manual. The radioactive material and items not meeting the release criteria were either sent to the Hazardous Waste Handling Facility (HWHF) for disposal or transferred to other locations approved for radioactive material. The D&D was undertaken by the Radiation Protection Group of LBNL`s Environment, Health and Safety (EH&S) Division at the request of the Materials Sciences Division. Current and past use of radioactive material in both Rooms 248 and 250 necessitated the D&D in order to release both rooms for nonradioactive work. (1) Room 248 was designated a {open_quotes}controlled area.{close_quotes} There was contained radioactive material in some of the equipment. The previous occupants of Room 248 had worked with radioactive materials. (2) Room 250 was designated a {open_quotes}Radioactive Materials Management …
Date:
May 1, 1996
Creator:
Garabedian, G.
Object Type:
Report
System:
The UNT Digital Library
A design guide for energy-efficient research laboratories
This document--A Design Guide for Energy-Efficient Research Laboratories--provides a detailed and holistic framework to assist designers and energy managers in identifying and applying advanced energy-efficiency features in laboratory-type environments. The Guide fills an important void in the general literature and compliments existing in-depth technical manuals. Considerable information is available pertaining to overall laboratory design issues, but no single document focuses comprehensively on energy issues in these highly specialized environments. Furthermore, practitioners may utilize many antiquated rules of thumb, which often inadvertently cause energy inefficiency. The Guide helps its user to: introduce energy decision-making into the earliest phases of the design process, access the literature of pertinent issues, and become aware of debates and issues on related topics. The Guide does focus on individual technologies, as well as control systems, and important operational factors such as building commissioning. However, most importantly, the Guide is intended to foster a systems perspective (e.g. right sizing) and to present current leading-edge, energy-efficient design practices and principles.
Date:
September 24, 1996
Creator:
Wishner, N.; Chen, A.; Cook, L.; Bell, G. C.; Mills, E.; Sartor, D. et al.
Object Type:
Report
System:
The UNT Digital Library
Production planning tools and techniques for agile manufacturing
Effective use of resources shared among multiple products or processes is critical for agile manufacturing. This paper describes development and implementation of a computerized model to support production planning in a complex manufacturing system at Pantex Plant. The model integrates two different production processes (nuclear weapon dismantlement and stockpile evaluation) which use common facilities and personnel, and reflects the interactions of scheduling constraints, material flow constraints, and resource availability. These two processes reflect characteristics of flow-shop and job-shop operations in a single facility. Operational results from using the model are also discussed.
Date:
October 1, 1996
Creator:
Kjeldgaard, E. A.; Jones, D. A.; List, G. F. & Turnquist, M. A.
Object Type:
Article
System:
The UNT Digital Library
Planning tools and techniques for production evaluation and disassembly
This paper describes the development and implementation of a computerized model to support production planning in a specialized type of remanufacturing facility, the Pantex Plant operated for the US Department of Energy. The model integrates two different production processes (nuclear weapon dismantlement and stockpile evaluation) which use common facilities and personnel, and reflects the interactions of scheduling constraints, material flow constraints and resource availability. These two processes reflect characteristics of flow-shop and job-shop operations in a single facility. Operational results from using the model are also discussed.
Date:
December 1, 1996
Creator:
Kjeldgaard, E. A.; List, G. F.; Turnquist, M. A. & Jones, D. A.
Object Type:
Article
System:
The UNT Digital Library
Thermal loading study for FY 1996. Volume 1
The primary objective of this study was to provide recommendations for Mined Geologic Disposal System requirements affected by thermal loading that will provide sufficient definition to facilitate development of design concepts and support life cycle cost determinations. The study reevaluated and/or redefined selected thermal goals used for design and are currently contained in the requirements documents or the Controlled Design Assumption Document. The study provided recommendations as to what, if any, actions (such as edge loading and limiting of the heat variability between waste packages) are needed and must be accommodated in the design. Additionally, the study provided recommendations as to what alternative thermal loads should be maintained for continued flexibility. Section 1 provides the study objective, background, scope, and organization of the report. Section 2 documents the requirements and standards to include quality assurance (QA) requirements, any requirements used or evaluated, and the inputs and assumptions considered. Section 3 provides the analysis and recommendations for the thermal goals reevaluation. Section 4 discusses the evaluation of edge loading and provides conclusions. Section 5 provides the analyses done to establish recommendations as to what requirements need to be implemented to either limit or manage the amount of heat output variability that …
Date:
November 8, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Surface water supply for the Clearlake, California Hot Dry Rock Geothermal Project
It is proposed to construct a demonstration Hot Dry Rock (HDR) geothermal plant in the vicinity of the City of Clearlake. An interim evaluation has been made of the availability of surface water to supply the plant. The evaluation has required consideration of the likely water consumption of such a plant. It has also required consideration of population, land, and water uses in the drainage basins adjacent to Clear Lake, where the HDR demonstration project is likely to be located. Five sources were identified that appear to be able to supply water of suitable quality in adequate quantity for initial filling of the reservoir, and on a continuing basis, as makeup for water losses during operation. Those sources are California Cities Water Company, a municipal supplier to the City of Clearlake; Clear Lake, controlled by Yolo County Flood Control and Water Conservation District; Borax Lake, controlled by a local developer; Southeast Regional Wastewater Treatment Plant, controlled by Lake County; and wells, ponds, and streams on private land. The evaluation involved the water uses, water rights, stream flows, precipitation, evaporation, a water balance, and water quality. In spite of California`s prolonged drought, the interim conclusion is that adequate water is available …
Date:
March 1, 1996
Creator:
Jager, A. R.
Object Type:
Report
System:
The UNT Digital Library
Mixed waste focus area integrated master schedule (current as of May 6, 1996)
The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) is to provide acceptable treatment systems, developed in partnership with users and with the participation of stakeholders, tribal governments, and regulators, that are capable of treating the Department of Energy`s (DOE`s) mixed wastes. In support of this mission, the MWTA produced the Mixed Waste Focus Area Integrated Technical Baseline Report, Phase I Volume 1, January 16, 1996, which identified a prioritized list of 30 national mixed waste technology deficiencies. The MWFA is targeting funding toward technology development projects that address the current list of deficiencies. A clear connection between the technology development projects and the EM-30 and EM-40 treatment systems that they support is essential for optimizing the MWFA efforts. The purpose of the Integrated Master Schedule (IMS) is to establish and document these connections and to ensure that all technology development activities performed by the MWFA are developed for timely use in those treatment systems. The IMS is a list of treatment systems from the Site Treatment Plans (STPs)/Consent Orders that have been assigned technology development needs with associated time-driven schedules, Technology deficiencies and associated technology development (TD) needs have been identified for each treatment system …
Date:
May 1, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library