Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands (open access)

Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands

In June 1975 a radiological survey was conducted of the terrestrial environment of Bikini and Eneu islands (Bikini Atoll) to evaluate the potential radiation dose to the returning Bikini population. In this report, we present measurements of the radionuclide concentration in soil profiles and in dominant species of edible and nonedible, indicator plants. The use of these data to derive relationships to predict the plant uptake of radionuclides from soil is described. Approximately 620 soil and vegetation samples from Bikini and Eneu Islands were analyzed by Ge(Li) gamma spectrometry and by wet chemistry. The predominant radionuclides in these samples were /sup 60/Co, /sup 90/Sr, /sup 137/Cs, /sup 239,240/Pu, /sup 241/Pu, and /sup 241/Am.
Date: January 21, 1977
Creator: Colsher, C. S.; Robison, W. L. & Gudiksen, P. H.
System: The UNT Digital Library
Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR] (open access)

Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the effect of molten fuel on reactor structural or sacrificial material.
Date: March 21, 1978
Creator: unknown
System: The UNT Digital Library
Powerplant Productivity Improvement Study: project summary report (open access)

Powerplant Productivity Improvement Study: project summary report

Key findings from the Illinois Powerplant Productivity Improvement Study are: (1) the historic performance (equivalent availability) of large generating units in Illinois is below national average performance; (2) cost-effective opportunities to improve performance exist, and utilities pursue many of these; (3) there are no strong regulatory disincentives to the undertaking of productivity improvement projects, but no strong incentives either; (4) current utility practices, procedures, and management philosophy toward improved productivity are being strengthened; (5) areas in which immediate attention is warranted include application of reliability engineering tools to the analysis of powerplant availability and more vigorous pursuit of opportunities for performance improvements; (6) DOE systematic methodology for analysis of productivity improvement projects was demonstrated at three units and found to be useful; (7) the potential for improved productivity was estimated to be of the order of 2% in planned and forced outage rates; (8) if a 5% improvement were to be attained, cumulative (through 1990) constant-dollar benefits would be approximately $500 million; (9) formula regulatory incentive mechanisms are presently in a developmental or experimental phase, but adoption by the State of Illinois does not appear warranted at this time; and (10) the Illinois Commerce Commission can encourage improved productivity by …
Date: December 21, 1979
Creator: unknown
System: The UNT Digital Library
Three-dimensional temperature history of a multipass filled weldment. Part 2. [HEATINGS] (open access)

Three-dimensional temperature history of a multipass filled weldment. Part 2. [HEATINGS]

Computer simulation of the three-dimensional temperature history in a multipass filled weldment was attempted by modifying a transient heat transfer code, HEATING5. The model includes temperature-dependent physical parameters, radiation and convection heat losses, turbulent and laminar convection in the molten pool, and variable arc velocity, intensity, and weld geometry. The model requires approximately 28 CPU min to simulate one second of welding. 15 figures, 8 tables.
Date: December 21, 1976
Creator: Pinkowish, J.A. & Whitman, P.K.
System: The UNT Digital Library
Volume reduction system for solid and liquid TRU waste from the nuclear fuel cycle: October--December 1977 (open access)

Volume reduction system for solid and liquid TRU waste from the nuclear fuel cycle: October--December 1977

A bench-scale incinerator for the investigation of unusual particulate and gaseous radioactive material in the incinerator off-gas was assembled and equipment checkout was begun. Modifications to a glovebox to be used for the demonstration phase of incinerator-ash immobilization are approximately 80% completed with demonstration to begin next quarter. The curing time for ash-cement pressed pellets was optimized by periodic crush-strength testing of open-air and underwater cured samples. Leach tests were performed at 70 and 100/sup 0/C to simulate normal and extreme storage conditions. Long-term leach tests were initiated on plutonium-238 doped ash-cement pressed pellets in distilled water at ambient temperature. Pressed pellets of bone char, ash, and sludge-ash in several mixtures were fabricated and tested to establish pressing and curing parameters. Leach tests were also performed on bone char-cement pressed pellets. Curing studies have been conducted on the pressed pellet matrix to define differences between curing in the open atmosphere and under water. Leachability studies have been initiated on the pressed pellet ash/cement matrix in distilled water at ambient, 70 and 100/sup 0/C. Also, leachability studies on doped plutonium-238 pressed ash/cement pellets and pressed bone char/cement pellets in distilled water at ambient temperature have been conducted. Compressive strengths of bone …
Date: April 21, 1978
Creator: Luthy, D. F. & Bond, W.H.
System: The UNT Digital Library
PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100 (open access)

PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100

Selected reduced instrument responses and analyses of the indicated phenomena are presented for Thermal-Hydraulic Test Facility (THTF) test series 100, which is part of the PWR Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomena that govern the energy transfer and transport processes occurring during a postulated loss-of-coolant accident in a pressurized-water reactor system. Comparisons are made between the trends indicated by the reduced instrument responses and the thermal-hydraulic transient simulator RELAP4/MOD5 (update 2) to aid in understanding the phenomenological sequences. The results of verification studies of RELAP's performance in prediction of the THTF data are presented.
Date: October 21, 1977
Creator: Hedrick, R. A.; Craddick, W. G.; Turnage, K. G. & Hyman, C. R.
System: The UNT Digital Library
Commercialization of a High Energy Neutral Beam Ion Source. Final Report (open access)

Commercialization of a High Energy Neutral Beam Ion Source. Final Report

This final report summarizes the effort and presents the results of a Phase II fabrication effort to build an industrial prototype of the LBL developed high energy neutral beam source. The effort was primarily concentrated on incorporating hard vacuum dielectric seals and a ceramic high voltage accelerator insulator. Several other design changes were incorporated for cost, reliability or life improvements to include: (1) accelerator grid locating dowel pins to aid final alignment, (2) plasma source to accelerator captive fasteners to aid filament replacement during source maintenance, (3) molybdenum cooling tubes on all accelerator grids, (4) additional fasteners in the plasma generator to facilitate hard seals, (5) modified suppressor grid rails and holders to simplify final grid alignment, (6) adjusting screws on exit grid rail holders to simplify final grid alignment, (7) addition of adjusting screws to the grid end pieces to simplify alignment, and (8) addition of accelerator hat shims to allow two different grid positioning locations.
Date: December 21, 1979
Creator: unknown
System: The UNT Digital Library
Chemistry research and development. Research and development semiannual progress report, January--June 1977 (open access)

Chemistry research and development. Research and development semiannual progress report, January--June 1977

Results of investigations and developmental activities are reported in chemical research, component research, instrumental and statistical systems, pilot plant research, and process chemistry and instrumentation. (JRD)
Date: October 21, 1977
Creator: Miner, F. J.
System: The UNT Digital Library
Report on the reconnaissance resistivity survey in the East Mesa area, Imperial County, California for U. S. Department of the Interior, Bureau of Reclamation (open access)

Report on the reconnaissance resistivity survey in the East Mesa area, Imperial County, California for U. S. Department of the Interior, Bureau of Reclamation

A section of notes on geothermal exploration using the resistivity method precedes the main body of the paper. Field data from the Broadlands Area of New Zealand, Java, and the Imperial Valley, California are included. The reconnaissance resistivity survey recently completed in the East Mesa Area confirmed that a broad zone of low resistivities at depth extends through the area in a NNW direction. The interpretation of the resistivity data and the location of the resistivity lows at depth is much less definite in the Imperial Valley than it is in other areas of geothermal exploration. This is due to the extremely low background level of resistivities. The low resistivities in the Imperial Valley are due to the high porosity of the sediments and the high salinity of the solutions contained within the rock. The expected decrease in resistivity due to elevated temperature is much more difficult to detect in this environment. Edges of the zones of low resistivities have been delineated in almost all directions. (JGB)
Date: January 21, 1974
Creator: Bell, B.S. & Hallof, P.G.
System: The UNT Digital Library
Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report (open access)

Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report

Activities performed in the Near Term Hybrid Vehicle (NTHV) program which studied the technical, economic, and fuel conservation aspects of replacing new 1985 full sized passenger cars in the US with automobiles having combination heat engines and electric motor power are summarized. These studies included NTHV design for the body power units, transmission system, and controls; evaluation of alternative strategies; the fuel conservation expected; goals for vehicle performance, safety and reliability; economic analysis, and mathematical models for use in the computer-aided design of the optimum performance NTHV. (LCL)
Date: September 21, 1979
Creator: Montalenti, P. & Piccolo, R.
System: The UNT Digital Library
Decommissioning of Division of Military Application equipment at Richland Operations Office for period ending March 31, 1975 (open access)

Decommissioning of Division of Military Application equipment at Richland Operations Office for period ending March 31, 1975

The scope of the decommissioning work provides for (1) the removal of all Division of Military Application (DH) fabrication and inspection equipment held in standby status in the 234-5Z Building, (2) disposition of all contaminated equipment and materials removed by packaging for 20-year retrievable storage, (3) reclamation of salvageable materials and equipment for use on site by other Energy Research and Development Administration contractors, and (4) restoration of cleared-out areas for other future Richland Operations Office programs.
Date: April 21, 1975
Creator: unknown
System: The UNT Digital Library
Properties of Kel F-800 polymer (open access)

Properties of Kel F-800 polymer

Kel F-800 fluorocarbon polymer has been selected as the binder for the TATB explosive in the B77 bomb. Kel F-800 is a 3M copolymer derived from the monomers chlorotrifluorethylene (CTFE) and vinylidine fluoride (VF/sub 2/). To understand and define Kel F-800 in relation to its intended use, as well as to generate guidelines for controlling the WR material, a thorough evaluation of its properties and the expected variations from different production lots was made. The research showed that Kel F-800 varies in both mechanical and thermal properties because of its high Tg (glass transition temperature) and because of its crystallinity. However, no evidence that these variabilities are detrimental to any of the end-use properties of Kel F-800 was found.
Date: July 21, 1977
Creator: Cady, W.E. & Caley, L.E.
System: The UNT Digital Library
Slicing of silicon into sheet material. Final report, January 9, 1976-September 30, 1979 (open access)

Slicing of silicon into sheet material. Final report, January 9, 1976-September 30, 1979

Complete results, from raw data to interpretation to recommendations, of a program to investigate the use of multiblade slurry sawing to produce silicon wafers from ingots are presented. During the course of this program, the commercially available state of the art process was improved by 20% in terms of area of silicon wafers produced from an ingot. The process was improved 34% on an experimental basis. Production of 20 wafers per centimeter length of 100 mm diameter ingot is now possible on a production basis. Economic analyses presented show that further improvements are necessary to approach the desired wafer costs, mostly reduction in expendable materials costs. Tests which indicate that such reduction is possble are included, although demonstration of such reduction was not completed. A new, large capacity saw was designed and tested. Performance comparable with current equipment (in terms of number of wafers/cm) was demonstrated. Improved performance was partially demonstrated, but problems (both mechanical and of unknown origin) precluded full demonstration of improved performance.
Date: September 21, 1979
Creator: Fleming, J R; Holden, S C & Wolfson, R G
System: The UNT Digital Library
Sixty keV D/sup -/ beams using double charge-exchange system (open access)

Sixty keV D/sup -/ beams using double charge-exchange system

A D/sup -/ beam with current greater than 100 ma was accelerated to 60 kV. The beam, with pulse length 10 ms, was generated by charge-exchange in cesium vapor. The physics of generation, propagation at low energy, and acceleration is discussed.
Date: September 21, 1977
Creator: Hooper, E. B. Jr.; Anderson, O. A.; Orzechowski, T. J. & Poulsen, P.
System: The UNT Digital Library
Thermal analysis of LOFT containment vessel penetrations S-5E and S-6A (open access)

Thermal analysis of LOFT containment vessel penetrations S-5E and S-6A

Thermal analysis of the LOFT containment vessel penetration S-6A was conducted for steady-state operation and blowdown transients. Penetration S-6A is a 20-inch pipe through which passes a 10-inch pipe from the steam generator containing 600/sup 0/F steam. Recommendations for penetration S-5E were based on the analysis of penetration S-6A. Penetration S-5E is an 18-inch pipe through which pass a 4-inch pipe containing the steam generator feedwater at 430/sup 0/F and a 0.5-inch pipe containing sample water at 600/sup 0/F. The thermal analysis is necessary to determine the maximum temperature gradient in the containment vessel around the penetrations. The outside of the penetrations protrude into a room adjacent to the containment vessel which will be maintained at a minimum temperature of 50/sup 0/F. The steady-state temperature inside the containment vessel was assumed to be 100/sup 0/F. Table I of LOFT Containment Vessel Specification S-1 was used for inside transient temperatures.
Date: April 21, 1970
Creator: Condie, K.G.
System: The UNT Digital Library
Development of Electrochemical Photovoltaic Cells. Second Technical Progress Report, August 1, 1979-October 31, 1979 (open access)

Development of Electrochemical Photovoltaic Cells. Second Technical Progress Report, August 1, 1979-October 31, 1979

The development of stable, efficient, photoelectrochemical cells based on silicon and gallium arsenide in non-aqueous electrolyte systems is being investigated. Redox reactions of ferrocene, anthracene and anthraquinone have been studied on platinum and n-silicon electrodes. The latter have been further characterized by differential capacitance measurements. Cells and equipment have been designed and set up for long-term stability studies.
Date: November 21, 1979
Creator: Austin, A. E.; Byker, H. J. & Brooman, E. W.
System: The UNT Digital Library
Nerva Fuel Element Development Program Summary Report - July 1966 through June 1972 Extrusion Studies (open access)

Nerva Fuel Element Development Program Summary Report - July 1966 through June 1972 Extrusion Studies

This part of the completion report pertaining to the NERVA graphite fuel element program covers data collected during the extrusion studies. The physical properties of the fuel element reached the following values: coefficient of thermal expansion (CTE) - 7.0 x 10-6/o C (25 - l,OOOo C); modulus of elasticity - 1.5 x lo6 psi; flexural strength - - 8,000 psi; ultimate strain to failure - 5,500 pidin; good thermal stress resistance. Matrices were produced which could be vapor coated with crack-free films of zirconium carbide. The CTE of the matrix was almost equal to the CTE of the zirconium carbide coating.
Date: September 21, 1973
Creator: Napier, J. M.
System: The UNT Digital Library
Analysis of stirred-tank carbonation reactors. [Removal of /sup 14/CO/sub 2/ by reaction with Ca(OH)/sub 2/] (open access)

Analysis of stirred-tank carbonation reactors. [Removal of /sup 14/CO/sub 2/ by reaction with Ca(OH)/sub 2/]

The removal of CO/sub 2/ from air in a calcium hydroxide slurry-agitated reactor was investigated to aid the design of such vessels. Gas-liquid interfacial areas were calculated using theoretical rate expression and experimental data at specific operating conditions. A correlation for interfacial areas was then determined as a function of impeller speed, impeller diameter, gas flow rate, and concentration of the slurry. Decontamination factors were also determined.
Date: November 21, 1978
Creator: Sheppard, N.F.; Rizo-Patron, R.C. & Sun, W.H.
System: The UNT Digital Library
Pump, sodium, inducer, intermediate size (ISIP) (impeller/inducer/diffuser retrofit) (open access)

Pump, sodium, inducer, intermediate size (ISIP) (impeller/inducer/diffuser retrofit)

This specification defines the requirements for the Intermediate-Size Inducer Pump (ISIP), which is to be made by replacing the impeller of the FFTF Prototype Pump with a new inducer, impeller, diffuser, seal, and necessary adapter hardware. Subsequent testing requirements of the complete pump assembly are included.
Date: April 21, 1978
Creator: Paradise, D.R.
System: The UNT Digital Library
Water-molten uranium hazard analysis. Final report. LATA report No. 92 (open access)

Water-molten uranium hazard analysis. Final report. LATA report No. 92

The hazard potential of cooling water leakage into the crucible of molten uranium in the MARS laser isotope separation experiment was investigated. A vapor-phase explosion is highly unlikely in any of the scenarios defined for MARS. For the operating basis accident, the gas pressure transient experienced by the vessel wall is 544 psia peak with a duration of 200 ..mu..s, and the peak hoop stress is about 20,000 psi in a 0.5-in. wall. Design and procedural recommendations are given for reducing the hazard. (DLC)
Date: August 21, 1979
Creator: Hughes, P.S.; Rigdon, L.D. & Donham, B.J.
System: The UNT Digital Library
LCPT: a program for finding linear canonical transformations. [In MACSYMA] (open access)

LCPT: a program for finding linear canonical transformations. [In MACSYMA]

This article describes a MACSYMA program to compute symbolically a canonical linear transformation between coordinate systems. The difficulties in implementation of this canonical small physics problem are also discussed, along with the implications that may be drawn from such difficulties about widespread MACSYMA usage by the community of computational/theoretical physicists.
Date: May 21, 1979
Creator: Char, B.W. & McNamara, B.
System: The UNT Digital Library
Thermal insulation system design and fabrication specification (nuclear) for the Clinch River Breeder Reactor plant (open access)

Thermal insulation system design and fabrication specification (nuclear) for the Clinch River Breeder Reactor plant

This specification defines the design, analysis, fabrication, testing, shipping, and quality requirements of the Insulation System for the Clinch River Breeder Reactor Plant (CRBRP), near Oak Ridge, Tennessee. The Insulation System includes all supports, convection barriers, jacketing, insulation, penetrations, fasteners, or other insulation support material or devices required to insulate the piping and equipment cryogenic and other special applications excluded. Site storage, handling and installation of the Insulation System are under the cognizance of the Purchaser.
Date: July 21, 1978
Creator: unknown
System: The UNT Digital Library
Evaluation of H/sub 2/S control technology for geothermal energy sources (open access)

Evaluation of H/sub 2/S control technology for geothermal energy sources

This study was conducted to identify processes that are most applicable for control of H/sub 2/S from geothermal sources. Both vapor-dominated and liquid-dominated sources were considered within the electric power generation category. The source characteristics, H/sub 2/S control requirements, and applicable technologies are discussed for the two geothermal sources. An evaluation of the applicable control technology indicates that there are three major approaches for H/sub 2/S removal. These are (a) upstream cleaning (ahead of the power plant), (b) removal of H/sub 2/S from condenser vent emissions, and (c) H/sub 2/S removal from cooling water, including condensate. The most promising processes for these emission points, based on current information, are as follows: the EIC process for upstream cleaning of liquid-dominated sources. For condenser vent emissions, the Stretford process appears to be most applicable; for cooling tower emissions, the iron catalyst process, followed by the H/sub 2/O/sub 2/ process, seems most appropriate.
Date: November 21, 1978
Creator: unknown
System: The UNT Digital Library
Reactor for simulation and acceleration of solar ultraviolet damage (open access)

Reactor for simulation and acceleration of solar ultraviolet damage

An environmental test chamber providing acceleration of uv radiation and precise temperature control (+- 1/sup 0/C) has been designed, constructed and tested. This chamber allows acceleration of solar ultraviolet up to 30 suns while maintaining temperature of the absorbing surface at 30/sup 0/C to 60/sup 0/C). This test chamber utilizes a filtered medium pressure mercury arc as the source of radiation, and a combination of selenium radiometer and silicon radiometer to monitor solar ultraviolet (295 to 340 nm) and total radiant power output, respectively. Details of design and construction and operational procedures are presented along with typical test data. The test chamber was designed for accelerated testing of solar cell modules.
Date: September 21, 1979
Creator: Laue, E. & Gupta, A.
System: The UNT Digital Library