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Materials for protective concealment
Discusses protective concealment (camouflage) as it matters to the soldier. Covers materials and uses as well as other equipment to be employed.
Date:
October 7, 1942
Creator:
United States. War Department.
Object Type:
Book
System:
The UNT Digital Library
Carbon Calculator for Land Use Change From Biofuels Production (Cclub). Users' Manual and Technical Documentation.
The Carbon Calculator for Land Use Change from Biofuels Production (CCLUB) calculates carbon emissions from land use change (LUC) for four different ethanol production pathways including corn grain ethanol and cellulosic ethanol from corn stover, miscanthus, and switchgrass. This document discusses the version of CCLUB released May 31, 2012 which includes corn, as did the previous CCLUB version, and three cellulosic feedstocks: corn stover, miscanthus, and switchgrass. CCLUB calculations are based upon two data sets: land change areas and above- and below-ground carbon content. Table 1 identifies where these data are stored and used within the CCLUB model, which is built in MS Excel. Land change area data is from Purdue University's Global Trade Analysis Project (GTAP) model, a computable general equilibrium (CGE) economic model. Section 2 describes the GTAP data CCLUB uses and how these data were modified to reflect shrubland transitions. Feedstock- and spatially-explicit below-ground carbon content data for the United States were generated with a surrogate model for CENTURY's soil organic carbon sub-model (Kwon and Hudson 2010) as described in Section 3. CENTURY is a soil organic matter model developed by Parton et al. (1987). The previous CCLUB version used more coarse domestic carbon emission factors. Above-ground …
Date:
June 7, 2012
Creator:
Mueller, S; Dunn, JB; Wang, M (Energy Systems) & Chicago), (Univ. of Illinois at
Object Type:
Report
System:
The UNT Digital Library
GDCT user`s manual
This manual provides the user on how to use the Graphical Database Configuration Tool (GDCT) to build EPICS databases and visualize links between records and process variables.
Date:
October 7, 1993
Creator:
Kowalkowski, J.
Object Type:
Report
System:
The UNT Digital Library
User's manual for the CORTES GRAPHICS PACKAGE GRFPAK
This report provides necessary user information to implement and use a graphics package for the CORTES finite-element computer programs. Complete input instructions are provided. Sample input and output are given.
Date:
July 7, 1977
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Transportable Xenon Laboratory (TXL-1) Operations Manual
The Transportable Xenon Laboratory Operations Manual is a guide to set up and shut down TXL, a fully contained laboratory made up of instruments to identify and measure concentrations of the radioactive isotopes of xenon by taking air samples and analyzing them. The TXL is housed in a standard-sized shipping container. TXL can be shipped to and function in any country in the world.
Date:
March 7, 2011
Creator:
Thompson, Robert C.; Stewart, Timothy L.; Willett, Jesse A. & Woods, Vincent T.
Object Type:
Report
System:
The UNT Digital Library
User's Manual for the FEHM Application-A Finite-Element Heat- and Mass-Transfer Code
This document is a manual for the use of the FEHM application, a finite-element heat- and mass-transfer computer code that can simulate nonisothermal multiphase multicomponent flow in porous media. The use of this code is applicable to natural-state studies of geothermal systems and groundwater flow. A primary use of the FEHM application will be to assist in the understanding of flow fields and mass transport in the saturated and unsaturated zones below the proposed Yucca Mountain nuclear waste repository in Nevada. The equations of heat and mass transfer for multiphase flow in porous and permeable media are solved in the FEHM application by using the finite-element method. The permeability and porosity of the medium are allowed to depend on pressure and temperature. The code also has provisions for movable air and water phases and noncoupled tracers; that is, tracer solutions that do not affect the heat- and mass-transfer solutions. The tracers can be passive or reactive. The code can simulate two-dimensional, two-dimensional radial, or three-dimensional geometries. In fact, FEHM is capable of describing flow that is dominated in many areas by fracture and fault flow, including the inherently three-dimensional flow that results from permeation to and from faults and fractures. …
Date:
July 7, 1997
Creator:
Zyvoloski, George A.; Robinson, Bruce A.; Dash, Zora V. & Trease, Lynn L.
Object Type:
Report
System:
The UNT Digital Library
Technical description of the new SS accountability program on the IBM-709
The SSA 100 program will compute the buildup and decay of SS materials, (gms Pu, U-235 burnout and uranium burnout) in fuel that has been irradiated in any of the Hanford reactors. The routine input data for the program are the IBM production records supplied by the Production Forecasting and Scheduling Operation. The purpose of this program is to compute and prepare an accurate accountabilty report with a minimum of manual effort. This can either be a report for fuel discharges from the reactors or a report of the entire month end reactor inventory. It is not the purpose of this report to describe in detail the data processing techniques used to provide the accountability reports, this will be left to the discretion of the SS Accountability Operation and the programer. The purpose of this report is to present (1) the technical methods that are fundamental to the program, (2) the necessary instructions that are necessary to make changes or include additional fuel data on the data tape and (3) the necessary instructions such that buildup and decay data can be obtained for fuel elements on a non-routine basis.
Date:
January 7, 1960
Creator:
Richey, C. R.
Object Type:
Report
System:
The UNT Digital Library
HANSF 1.3 Users Manual FAI/98-40-R2 Hanford Spent Nuclear Fuel (SNF) Safety Analysis Model [SEC 1 and 2]
The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.
Date:
October 7, 1999
Creator:
Duncan, D. R.
Object Type:
Report
System:
The UNT Digital Library
Technical Safety Requirements for the Waste Storage Facilities
This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are …
Date:
September 7, 2007
Creator:
Larson, H L
Object Type:
Report
System:
The UNT Digital Library
Weatherization Assistance Program Technical Assistance Center
The following is a synopsis of the major achievements attributed to the operation of the Weatherization Assistance Program Technical Assistance Center (WAPTAC) by the National Association for State Community Services Programs (NASCSP). During the past five years, the WAPTAC has developed into the premier source for information related to operating the Weatherization Assistance Program (WAP) at the state and local levels. The services provide through WAPTAC include both virtual technical support as well as hands-on training and instruction in classroom and in the field. The WAPTAC achieved several important milestones during its operation including the establishment of a national Weatherization Day now celebrated in most states, the implementation of a comprehensive Public Information Campaign (PIC) to raise the awareness of the Program among policy makers and the public, the training of more than 150 new state managers and staff as they assume their duties in state offices around the country, and the creation and support of a major virtual information source on the Internet being accessed by thousands of staff each month. The Weatherization Assistance Program Technical Assistance Center serves the Department of Energy's (DOE) Office of Weatherization and Intergovernmental Program as a valuable training and technical assistance resource for …
Date:
January 7, 2009
Creator:
Adams, Robert
Object Type:
Report
System:
The UNT Digital Library
Metallurgical Project Technical Division Program Authorizations
None
Date:
April 7, 1944
Creator:
Cooper, C. M.
Object Type:
Report
System:
The UNT Digital Library
Nuclear health and safety technical specifications. Revision 1
This information contained in this document is a compilation of technical specifications applicable to the process limits for the eight existing Hanford Production Reactors. These technical specifications, together with other administrative procedures and controls, would define the limits of reactor operation and would establish administrative methods for obtaining approvals, reviews, and procedures for making changes. Operating and performance restrictions are reported for: reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor scram set points, reactor fuel loadings, reactor coolant system, reactor confinement, test facilities, and code compliance.
Date:
December 7, 1961
Creator:
Gilbert, W. D.
Object Type:
Report
System:
The UNT Digital Library
Alternative Energy Center, Final Scientific/Technical Report
The Lansing Community College Alternative Energy Center was created with several purposes in mind. The first purpose was the development of educational curricula designed to meet the growing needs of advanced energy companies that would allow students to articulate to other educational institutions or enter this growing workforce. A second purpose was the professional development of faculty and teachers to prepare them to train tomorrow's workforce and scholars. Still another purpose was to design, construct, and equip an alternative energy laboratory that could be used for education, demonstration, and public outreach. Last, the Center was to engage in community outreach and education to enhance industry partnerships, inform decision makers, and increase awareness and general knowledge of hydrogen and other alternative energy technologies and their beneficial impacts on society. This project has enabled us to accomplish all of our goals, including greater faculty understanding of advanced energy concepts, who are now able to convey this knowledge to students through a comprehensive alternative energy curriculum, in a facility well-equipped with advanced technologies, which is also being used to better educate the public on the advantages to society of exploring alternative energy technologies.
Date:
September 7, 2007
Creator:
Dillman, Howard D. & Marshall, JaNice C.
Object Type:
Report
System:
The UNT Digital Library
Technical Direction and Laboratories FY 1999 Annual Report
This annual report summarize achievements and list reports issued by members of TD&L, NHC group during Fiscal Year (FY) 1999, (October 1, 1998 through September 30, 1999). This report, issued by this organization, describes work in support of the Hanford Site and other U S . Department of Energy, Richland Operations Office (DOE-RL) programs. It includes information on the organization make-up, interfaces, and mission of the group. The TD&L is a group of highly qualified personnel with diverse disciplines (primarily chemistry specialties) that provide process, analytical, and in-situ chemistry services to engineering customers. This year of operation and interfaces with other contract organizations consumed considerable administrative efforts. Attention was directed to the technical challenges presented by the changing roles, responsibilities, and priorities of Hanford programs.
Date:
September 7, 2000
Creator:
Crawford, B. A.
Object Type:
Report
System:
The UNT Digital Library
Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility
This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 …
Date:
September 7, 2007
Creator:
Larson, H L
Object Type:
Report
System:
The UNT Digital Library
OTEC platform configuration and integration. Volume II. Technical concept. Final report
The configuration, integration, and evaluation studies performed in the first phase of this contract resulted in a ranking of the most feasible platform candidates for commercial OTEC applications. On the basis of the results obtained from three individual contractors performing the same study, the Department of Energy made selections of two platform hulls for each contractor for conceptual designs. For Phase-II studies, M. Rosenblatt and Son, Inc. (MR and S) project team was given the SPAR and SPHERE platforms to perform not only conceptual designs for, but also cost and time schedules and sensitivity analyses. This is the second volume of a three-volume MR and S report, and it presents the results of conceptual designs for the two platforms, the facilities and equipment required for construction, deployment, and operation of these platforms, and cost estimates and time schedules. All conceptual design work is performed for the baseline site on West Coast of Florida. The cost differentials and other considerations involved with deploying the platforms in the New Orleans and Puerto Rico sites are also presented. As an end product of the complete study, the costs for the SPAR and the SPHERE platforms are reported both in terms of acquisition costs …
Date:
July 7, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
FAST FLUX TEST FACILITY MONTHLY INFORMAL TECHNICAL PROGRESS REPORT: MARCH 1969
This report was prepared by Battelle-Northwest under Contract No. AT(4S-l)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during March 1969.
Date:
April 7, 1969
Creator:
Astley, E. R.
Object Type:
Report
System:
The UNT Digital Library
Technical specification for the 1.5 Tesla superconducting solenoid for the BaBar detector. Revision 1
This document sets forth the specification of the BABAR superconducting solenoid and power supply which is being supplied to the BABAR collaboration by INSTITUTO NAZIONALE DI FISICA NUCLEARE (INFN). The solenoid will be installed in the BABAR detector which will be located at Interaction Region 2 (IR2) of the PEP II machine, a positron electron collider, presently under construction at the Stanford Linear Accelerator Center (SLAC) located in Menlo Park, California. The solenoid will become part of the BABAR detector which will be used in SLAC`s high energy physics program. Intense beams of electrons and positrons are made to collide inside the solenoid magnet. High field uniformity quality, precise mechanical alignment and long term stability are essential characteristics of the solenoid. INFN will set up a committee that will provide contractual and technical oversight throughout the design, fabrication and installation phases of the BABAR solenoid construction. That committee will be the final authority to resolve any differences between these specifications and the INFN supplied drawings, in addition to any differences between these specifications or the INFN supplied drawings and the proposals from the vendor. All submissions for approval to INFN whether for design changes, material approval, design submissions or others …
Date:
March 7, 1997
Creator:
O`Connor, T. G.; Bell, R.; Fabbricatore, P.; Giorgi, M. & Hitlin, D.
Object Type:
Report
System:
The UNT Digital Library
Technical Report on Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration
The Nature Conservancy participated in a Cooperative Agreement with the Department of Energy (DOE) National Energy Technology Laboratory (NETL) to explore the compatibility of carbon sequestration in terrestrial ecosystems and the conservation of biodiversity. The title of the research project was 'Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration'. The objectives of the project were to: (1) improve carbon offset estimates produced in both the planning and implementation phases of projects; (2) build valid and standardized approaches to estimate project carbon benefits at a reasonable cost; and (3) lay the groundwork for implementing cost-effective projects, providing new testing ground for biodiversity protection and restoration projects that store additional atmospheric carbon. This Final Technical Report discusses the results of the six tasks that The Nature Conservancy undertook to answer research needs while facilitating the development of real projects with measurable greenhouse gas reductions. The research described in this report occurred between July 1st 2001 and July 10th 2008. The specific tasks discussed include: Task 1: carbon inventory advancements; Task 2: emerging technologies for remote sensing of terrestrial carbon; Task 3: baseline method development; Task 4: third-party technical advisory panel meetings; Task 5: new project feasibility studies; and …
Date:
January 7, 2009
Creator:
Stanley, Bill; Brown, Sandra; Kant, Zoe & Gonzalez, Patrick
Object Type:
Report
System:
The UNT Digital Library
FAST FLUX TEST FACILITY MONTHLY INFORMAL TECHNICAL PROGRESS REPORT FEBRUARY 1969
This report was prepared by Battelle-Northwest under Contract No. AT (45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during February 1969.
Date:
March 7, 1969
Creator:
Astley, E. R.
Object Type:
Report
System:
The UNT Digital Library
FAST FLUX TEST FACILITY MONTHLY INFORMAL TECHNICAL PROGRESS REPORT OCTOBER 1969
This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during October 1969.
Date:
November 7, 1969
Creator:
Astely, E. R. & Cabell, C. P.
Object Type:
Report
System:
The UNT Digital Library
Aviation Safety: FAA Management Practices for Technical Training Mostly Effective; Further Actions Could Enhance Results
A letter report issued by the Government Accountability Office with an abstract that begins "One key way that the Federal Aviation Administration (FAA) makes air travel safer is to inspect the manufacture, operation, and maintenance of aircraft that fly in the United States. To better direct its resources, FAA is shifting from an inspection process that relied on spot-checks of compliance with regulations to one that evaluates operating procedures and analyzes inspection data to identify areas that pose the most risk to safety (called system safety). While FAA believes the new approach requires some technical knowledge of aircraft, Congress and GAO have long-standing concerns over whether FAA inspectors have enough technical knowledge to effectively identify risks. GAO reviewed the extent that FAA follows effective management practices in ensuring that inspectors receive up-to-date technical training. In addition, GAO is reporting on technical training that the aviation industry provides to FAA."
Date:
September 7, 2005
Creator:
United States. Government Accountability Office.
Object Type:
Report
System:
The UNT Digital Library
POC-scale testing of an advanced fine coal dewatering equipment/technique: Quarterly technical progress report,January--March 1997
Laboratory centrifugal dewatering tests were conducted to study the effects of anionic and cationic flocculants on filtration of PMCC compliance (low sulfur) and non-compliance (high sulfur) ultrafine coal slurry. The results obtained with compliance coal indicated that use of 30 g/t anionic flocculant reduced filter cake moisture from 32. 3 to 29.0 percent and increased solids recovery by two absolute percentage points. Use of cationic flocculant had no effects on solids recovery but lowered cake moisture to 27 percent at a dosage of 15 g/t. With the non-compliance coal slurry addition of 15 g/t anionic flocculant lowered cake moisture from 30 to 28.5 percent with marginal effects on solids recovery; addition of cationic flocculant reduced cake moisture by one absolute percentage point. Both flocculants showed marginal effects on solids recovery. Laboratory vacuum filter leaf filtration studies showed that use of flocculants considerably increased filtration kinetics. For example, addition of 15 g/t anionic flocculant to the compliance coal slurry increased filtration kinetics by 10 times and addition of 15 g/t.
Date:
May 7, 1997
Creator:
Tao, D.; Grappo, J. G. & Parekh, B. K.
Object Type:
Report
System:
The UNT Digital Library
Development and testing of industrial scale, coal-fired combustion system, Phase 3. Seventeenth quarterly technical progress report, January 1, 1996--March 31, 1996
In the first quarter of calendar year 1996, 9 days of combust-boiler tests were performed. Between these tests, modifications and improvements that were indicated by these tests were implemented. In January and early February, the modifications and installations indicated by the 6 days of testing in December 1995 were implemented. This was followed by 6 additional consecutive test days in mid- February. This was in turn followed by additional modifications, followed by a series of 3 one day, coal fired tests at end of March. These latter tests were the first ones in which slagging conditions were achieved in the combustor. The maximum thermal input was 13 MMBtu/hr, which equals two-thirds of the rated boiler heat input. The measured thermal, combustion, and slagging performance achieved in the combustor was superior to that achieved in the final series of tests conducted in Williamsport in 1993. The combustor-boiler facility is now ready for implementation of the task 5 site demonstration.
Date:
April 7, 1996
Creator:
Zauderer, B.
Object Type:
Report
System:
The UNT Digital Library