1-MWE Heat Exchangers for OTEC Final Design Report (open access)

1-MWE Heat Exchangers for OTEC Final Design Report

The design of a 1 MWe OTEC heat exchanger is documented, including the designs of the evaporator and associated systems, condenser, instrumentation, and materials for corrosion/erosion control and fabrication processes. (LEW)
Date: June 19, 1980
Creator: Sprouse, A.M.
Object Type: Report
System: The UNT Digital Library
64 kW concentrator Photovoltaics Application Test Center. Volume. Final report (open access)

64 kW concentrator Photovoltaics Application Test Center. Volume. Final report

Kaman Sciences Corporation has designed a 64 kW Concentrating Photovoltaic Applications Test Center (APTEC). The APTEC employs a combined concentrating photovoltaic array in a total energy system application for load sharing the electric and thermal demands of a large computer center with the interfaced electric and natural gas utility. The photovoltaic array is composed of two-axis tracking heliostats of Fresnel lens concentrating, silicon solar cell modules. The modules are cooled with a fluid which transfers heat to a ground coupled heat sink/storage unit for subsequent use in meeting the computer center's thermal load demand. The combined photovoltaic power system shares basic components - a power conditioning unit, batteries and thermal conditioning equipment - with the electric and natural gas utility service, improving the computer center's operating availability time and displacing a portion of the fossil fuel required to power the computer center with solar energy. The detailed system design is reported.
Date: June 1, 1980
Creator: Jardine, D.M. & Jones, D.W.
Object Type: Report
System: The UNT Digital Library
800-MWe HTGR-gas-turbine two-loop electric plant (open access)

800-MWe HTGR-gas-turbine two-loop electric plant

The design and development of the electric plant for the HTGR-Gas Turbine (GT) present a radical departure in accommodating the electrical requirements of the nuclear heat system and the balance of plant. To address not only these requirements but also codes and standards (for power plants and safety-grade systems), the evolution of the design dictates the application of innovative and unique solutions. The complexity of the GT plant and the criteria for nuclear power stations are substantial restraints and limit the availability of alternatives normally present in the development of a design and configuration. Objective of this report is to acquaint the reader with the electric design and to highlight those aspects of the electric plant which are unique. In addition, some insight will be presented on the impact of the plant configuration evolution on electric systems.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
850/sup 0/C VHTR plant technical description (open access)

850/sup 0/C VHTR plant technical description

This report describes the conceptual design of an 842-MW(t) process heat very high temperature reactor (VHTR) plant having a core outlet temperature of 850/sup 0/C (1562/sup 0/F). The reactor is a variation of the high-temperature gas-cooled reactor (HTGR) power plant concept. The report includes a description of the nuclear heat source (NHS) and of the balance of reactor plant (BORP) requirements. The design of the associated chemical process plant is not covered in this report. The reactor design is similar to a previously reported VHTR design having a 950/sup 0/C (1742/sup 0/F) core outlet temperature.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Actinide partitioning-transmutation program final report. I. Overall assessment (open access)

Actinide partitioning-transmutation program final report. I. Overall assessment

This report is concerned with an overall assessment of the feasibility of and incentives for partitioning (recovering) long-lived nuclides from fuel reprocessing and fuel refabrication plant radioactive wastes and transmuting them to shorter-lived or stable nuclides by neutron irradiation. The principal class of nuclides considered is the actinides, although a brief analysis is given of the partitioning and transmutation (P-T) of /sup 99/Tc and /sup 129/I. The results obtained in this program permit us to make a comparison of the impacts of waste management with and without actinide recovery and transmutation. Three major conclusions concerning technical feasibility can be drawn from the assessment: (1) actinide P-T is feasible, subject to the acceptability of fuels containing recycle actinides; (2) technetium P-T is feasible if satisfactory partitioning processes can be developed and satisfactory fuels identified (no studies have been made in this area); and (3) iodine P-T is marginally feasible at best because of the low transmutation rates, the high volatility, and the corrosiveness of iodine and iodine compounds. It was concluded on the basis of a very conservative repository risk analysis that there are no safety or cost incentives for actinide P-T. In fact, if nonradiological risks are included, the short-term …
Date: June 1, 1980
Creator: Croff, A. G.; Blomeke, J. O. & Finney, B. C.
Object Type: Report
System: The UNT Digital Library
Actinide Partitioning-Transmutation Program Final Report. V. Preconceptual designs and costs of partitioning facilities and shipping casks (appendix 3) (open access)

Actinide Partitioning-Transmutation Program Final Report. V. Preconceptual designs and costs of partitioning facilities and shipping casks (appendix 3)

This Appendix contains cost estimate documents for the Fuels Reprocessing Plant Waste Treatment Facility. Plant costs are summarized by Code of Accounts and by Process Function. Costs contribution to each account are detailed. Process equipment costs are detailed for each Waste Treatment Process. Service utility costs are also summarized and detailed.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Actinide partitioning-transmutation program. V. Preconceptual designs and costs of partitioning facilities and shipping casks, Appendix 4. Final report (open access)

Actinide partitioning-transmutation program. V. Preconceptual designs and costs of partitioning facilities and shipping casks, Appendix 4. Final report

This Appendix contains cost estimate documents for the Fuels Fabrication Plant Waste Treatment Facility. Plant costs are summarized by Code of Accounts and by Process Function. Costs contributing to each account are detailed. Process equipment costs are detailed for each Waste Treatment Process. Service utility costs are also summarized and detailed. Shipping cask costs are provided.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
ACTVE News, Volume 11, Number 6, June 1980 (open access)

ACTVE News, Volume 11, Number 6, June 1980

Newsletter issued by the Advisory Council for Technical-Vocational Education in Texas discussing news, events, and other relevant information related to technical and vocational education for adults in Texas.
Date: June 1980
Creator: Advisory Council for Technical-Vocational Education in Texas
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980 (open access)

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.
Date: June 25, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program: Topical report I, selection of candidate alloys. Volume 3. Selection of surface coating/substrate systems for screening creep and structural stability studies (open access)

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program: Topical report I, selection of candidate alloys. Volume 3. Selection of surface coating/substrate systems for screening creep and structural stability studies

Considering the high temperature, low O/sub 2/, high C environment of operation in the Very High Temperature Reactor (VHTR) Systems, the utilization of coatings is envisaged to hold potential for extending component lifetimes through the formation of stable and continuous oxide films with enhanced resistance to C diffusion. A survey of the current state of technology for high temperature coatings has been performed. The usefulness of these coatings on the Mo, Ni, and Fe base alloys is discussed. Specifically, no coating substitute was identified for TZM other than the well known W-3 (pack silicide) and Al/sub 2/O/sub 3/ forming coatings were recommended for the Fe and Ni base structural materials. Recommendations as to coating types and processng have been made based on the predicted VHTR component size, shape, base metal and operational environment. Four tests designed to evaluate the effects of selected combinations of coatings and substrate matrices are recommended for consideration.
Date: June 20, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced integrated safeguards at Barnwell (open access)

Advanced integrated safeguards at Barnwell

The development and initial performance testing of an advanced integrated safeguards system at the Barnwell Nuclear Fuel Plant (BNFP) is described. The program concentrates on the integration and coordination of physical security and nuclear materials control and accounting at a single location. Hardware and software for this phase have been installed and are currently being evaluated. The AGNS/DOE program is now in its third year of development at the BNFP.
Date: June 1, 1980
Creator: Bambas, Karl J. & Barnes, Lawrence D.
Object Type: Article
System: The UNT Digital Library
Advanced Reactor Safety Research Division. Quarterly Progress Report, January 1-March 31, 1980 (open access)

Advanced Reactor Safety Research Division. Quarterly Progress Report, January 1-March 31, 1980

The Advanced Reactor Safety Research Programs quarterly progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.
Date: June 1, 1980
Creator: Agrawal, A. K.; Cerbone, R. J. & Sastre, C.
Object Type: Report
System: The UNT Digital Library
Advanced Technology Section semiannual progress report, April 1-September 30, 1977. Volume 1. Biotechnology and environmental programs. [Lead Abstract] (open access)

Advanced Technology Section semiannual progress report, April 1-September 30, 1977. Volume 1. Biotechnology and environmental programs. [Lead Abstract]

Research efforts in six areas are reported. They include: centrifugal analyzer development; advanced analytical systems; environmental research; bioengineering research;bioprocess development and demonstration; and, environmental control technology. Individual abstracts were prepared for each section for ERA/EDB. (JCB)
Date: June 1, 1980
Creator: Pitt, W.W. Jr. & Mrochek, J.E. (comps.)
Object Type: Report
System: The UNT Digital Library
Aerial Gamma Ray and Magnetic Survey, Final Report: Harrison Quadrangle, Missouri and Arkansas (open access)

Aerial Gamma Ray and Magnetic Survey, Final Report: Harrison Quadrangle, Missouri and Arkansas

This report provides radiometric and magnetic data for the Harrison quadrangle of southern Missouri and northern Arkansas that was acquired and processed in May of 1980. Appendix A provides a detailed summary of data acquisition, processing, interpretation, and presentation methods; Appendix B contains a flight summary report for the quadrangle.
Date: June 1980
Creator: EG & G GeoMetrics
Object Type: Report
System: The UNT Digital Library
Aerial Gamma Ray and Magnetic Survey, Final Report: Springfield Quadrangle, Missouri (open access)

Aerial Gamma Ray and Magnetic Survey, Final Report: Springfield Quadrangle, Missouri

This report provides radiometric and magnetic data for the Springfield quadrangle in Missouri that was acquired and processed in May 1980. Appendix A provides a detailed summary of data acquisition, processing, interpretation, and presentation methods; Appendix B contains a flight summary report for the quadrangle.
Date: June 1980
Creator: EG & G GeoMetrics
Object Type: Report
System: The UNT Digital Library
Alaska: a guide to geothermal energy development (open access)

Alaska: a guide to geothermal energy development

Alaska's geothermal potential, exploration, drilling, utilization, and legal and institutional setting are covered. Economic factors of direct use projects are discussed. (MHR)
Date: June 1, 1980
Creator: Basescu, N.; Bloomquist, R.G.; Higbee, C.; Justus, D. & Simpson, S.
Object Type: Report
System: The UNT Digital Library
Alaska: a guide to geothermal energy development (open access)

Alaska: a guide to geothermal energy development

A brief overview is given of the geological characteristics of each region of the state as they relate to potential geothermal development. Those exploration methods which can lead to the siting of a deep exploration well are described. Requirements and techniques needed for drilling deeper higher temperature exploration and production wells are presented. Electrical generation, direct utilization, and indirect utilization are reviewed. Economic factors of direct use projects are presented. A general guide to the regulatory framework affecting geothermal energy development is provided. The general steps necessary to gain access to explore, develop, distribute, and use geothermal resources are outlined. (MHR)
Date: June 1, 1980
Creator: Basescu, N.; Bloomquist, R.G.; Higbee, C.; Justus, D. & Simpson, S.
Object Type: Report
System: The UNT Digital Library
Alaska Open-File Report 127 Assessment of Thermal Springs Sites in Southern Southeastern Alaska - Preliminary Results and Evaluation (open access)

Alaska Open-File Report 127 Assessment of Thermal Springs Sites in Southern Southeastern Alaska - Preliminary Results and Evaluation

Information has been gathered on 13 reported thermal-spring sites, 12 in southern Southeastern Alaska and one in western British Columbia. Five of the reported sites could not be substantiated by DGGS. The eight known thermal spring sites are associated with grainitic terrain and, except for Baker Island Hot Springs, occur within or near intensively fractured Cretaceous-age pluons of the Coast Range Batholith. Thermal-spring surface temperatures range from 21 C (Twin Lakes) to 91.5 C (Bailey Bay). The greatest discharge occurs at Chief Shakes hot springs (450 1pm). Bell Island Hot Springs, which has about a 100-1 pm discharge and a 70 C temperature, has had the most development. Two previously unreported thermal-spring sites, Barnes Lake warm springs and Bradfield hot springs, have a low rate of discharge and respective surface temperatures of about 25 and 54 C. The known thermal springs probably originate from circulation of meteoric waters through deep-seated fracture and fault systems. The chemical constituents of the alkali-sulfate to alkali-chloride thermal waters are probably derived from interaction of the deeply circulating meteoric waters with the granitic wall rocks. Chemical geothermometry suggests subsurface temperatures of 55 to 151 C. If waters are being heated solely by conduction from wall …
Date: June 1, 1980
Creator: Motyka, Roman J.; Moorman, Mary A. & Reeder, John W.
Object Type: Report
System: The UNT Digital Library
Aliphatic components of coal. Quarterly report, March-June 1980 (open access)

Aliphatic components of coal. Quarterly report, March-June 1980

Liquefaction of coal involves thermolysis of benzyl-oxygen and/or benzyl-benzyl bonds as the first step in the depolymerization. This view derives from NMR studies, studies with model compounds, and oxidative degradations with Na/sub 2/Cr/sub 2/O/sub 7/ and CF/sub 3/CO/sub 3/H/sub 2/. The best method for determining the amount of arylmethyl groups in coals is from the yield of acetic acid formed in oxidative degradation with CF/sub 3/CO/sub 3/H-H/sub 2/SO/sub 4/. The following observations and interpretations are made: a sharp increase in arylmethyl accompanies liquefaction in all five coals and in two coals studied earlier. This increase is the result of thermal cleavage to benzyl radicals and abstraction of hydrogen atoms by the benzyl radicals to form arylmethyl. All five coals give about the same percentage increase in arylmethyl after 90 mins of solvent refining, but not after 3 mins. This indicates that benzyl radicals form from more than one type of structure. Based on studies of model compounds, it is attractive to ascribe arylmethyl formation in 3 mins to cleavage of benzyl ethers and slower cleavage to bibenzyl structures. It might have been expected that the more arylmethyl, the more cleavage, and the more SRC. In fact the opposite is found. …
Date: June 1, 1980
Creator: Deno, N. C.; Cannon, C.; Curry, K.; Jones, A. D.; Potter, T. C.; Rakitsky, W. G. et al.
Object Type: Report
System: The UNT Digital Library
Alloy development for irradiation performance. Quarterly progress report for period ending March 31, 1980 (open access)

Alloy development for irradiation performance. Quarterly progress report for period ending March 31, 1980

This report is organized along topical lines in parallel to a Program Plan of the same title so that activities and accomplishments may be followed readily relative to that Program Plan. Thus, the work of a given laboratory may appear throughout the report. Chapters 1, 2, 8, and 9 review activities on analysis and evaluation, test methods development, status of irradiation experiments, and corrosion testing and hydrogen permeation studies, respectively. These activities relate to each of the alloy development paths. Chapters 3, 4, 5, 6, and 7 present the ongoing work on each alloy development path. The Table of Contents is annotated for the convenience of the reader.
Date: June 1, 1980
Creator: Ashdown, B.G. (comp.)
Object Type: Report
System: The UNT Digital Library
Alternative energy sources for non-highway transportation. Appendices (open access)

Alternative energy sources for non-highway transportation. Appendices

A planning study was made for DOE on alternate fuels for non-highway transportation (aircraft, rail, marine, and pipeline). The study provides DOE with a recommendation of what alternate fuels may be of interest to non-highway transportation users from now through 2025 and recommends R and D needed to allow non-petroleum derived fuels to be used in non-highway transportation. Volume III contains all of the references for the data used in the preliminary screening and is presented in 4 subvolumes. Volume IIIA covers the background information on the various prime movers used in the non-highway transportation area, the physical property data, the fuel-prime mover interaction and a review of some alternate energy forms. Volume IIIB covers the economics of producing, tranporting, and distributing the various fuels. Volume IIIC is concerned with the environment issues in production and use of the fuels, the energy efficiency in use and production, the fuel logistics considerations, and the overall ratings and selection of the fuels and prime movers for the detailed evaluation. Volume IIID covers the demand-related issues.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Alternative energy sources for non-highway transportation: executive summary (open access)

Alternative energy sources for non-highway transportation: executive summary

A planning study was made for DOE on alternate fuels for non-highway transportation (aircraft, rail, marine, and pipeline). The study provides DOE with a recommendation of what alternate fuels may be of interest to non-highway transportation users from now through 2025 and recommends R and D needed to allow non-petroleum derived fuels to be used in non-highway transportation. In the near term (present-1985), there is unlikely to be any major change in the fuels used in any of the four modes of transportation except that the average quality of the marine fuel is likely to get worse. In the mid-term period (1985-2000), there will be a transition to non-petroleum fuels, based primarily on shale oil derived liquids assuming a shale oil industry is started during this time.
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Alternative energy sources for non-highway transportation: technical section (open access)

Alternative energy sources for non-highway transportation: technical section

Eighteen different alternative fuels were considered in the preliminary screening, from three basic resource bases. Coal can be used to provide 13 of the fuels; oil shale was the source for three of the fuels; and biomass provided the resource base for two fuels not provided from coal. In the case of biomass, six different fuels were considered. Nuclear power and direct solar radiation were also considered. The eight prime movers that were considered in the preliminary screening are boiler/steam turbine; open and closed cycle gas turbines; low and medium speed diesels; spark ignited and stratified charge Otto cycles; electric motor; Stirling engine; free piston; and fuel cell/electric motor. Modes of transport considered are pipeline, marine, railroad, and aircraft. Section 2 gives the overall summary and conclusions, the future outlook for each mode of transportation, and the R and D suggestions by mode of transportation. Section 3 covers the preliminary screening phase and includes a summary of the data base used. Section 4 presents the methodology used to select the fuels and prime movers for the detailed study. Sections 5 through 8 cover the detailed evaluation of the pipeline, marine, railroad, and aircraft modes of transportation. Section 9 covers the …
Date: June 1, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Alternative institutional vehicles for geothermal district heating (open access)

Alternative institutional vehicles for geothermal district heating

The attributes of various institutional entities which might participate in various phases of geothermal heating applications are described. Public entities considered include cities, counties, and special districts. Private entities discussed include cooperative organizations and non-member-owned private enterprises. The powers, authority and manner of operation of each of the institutional entities are reviewed. Some of the public utility regulatory implications which may affect choices among available alternatives are considered. (MHR)
Date: June 1, 1980
Creator: Bressler, S.; Gardner, T.C.; King, D. & Nimmons, J.T.
Object Type: Report
System: The UNT Digital Library