Kilowatt Isotope Power System, Phase II Plan. Volume IV. Teledyne FSCD vs GDS (open access)

Kilowatt Isotope Power System, Phase II Plan. Volume IV. Teledyne FSCD vs GDS

This Volume contains Teledyne's input to the Kilowatt Isotope Power System Phase II Plan. Included is a description of the Flight System Heat Generation System, Flight System Radiator, Thermal Insulation Stability, GDS Heat Generation System and GDS Radiator.
Date: March 15, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Single particle behavior in plasmas (open access)

Single particle behavior in plasmas

The paper follows the history of a neutral atom or molecule into a plasma--ionization, dissociation, radiation,--until it becomes a set of charged particles moving in the electromagnetic fields of the plasma system. The various useful forms of the method of averaging are displayed and applied to calculation of constants of motion. The breakdown of these constants is discussed along with some of the implications for fusion systems.
Date: March 10, 1977
Creator: McNamara, B.
Object Type: Report
System: The UNT Digital Library
Development of a High Velocity Solid Particle Launcher for Laboratory Erosion Studies. [Reentry Vehicle Heat Shields] (open access)

Development of a High Velocity Solid Particle Launcher for Laboratory Erosion Studies. [Reentry Vehicle Heat Shields]

A solid particle launcher for laboratory erosion studies has been developed and successfully demonstrated. Performance of the launcher is predicted by a two-dimensional, time-dependent theoretical analysis to within the experimental uncertainty. The present device accelerates 100 μm diameter glass spheres to velocities of 2.1+/- 0.6 km/sec. The system is safe, reliable, and has a test repetition of about 2 shots/hour.
Date: March 1, 1975
Creator: Aeschliman, D. P.; Mulac, A. J.; Guzman, J. A.; Eaton, R. R. & Fox, R. L.
Object Type: Report
System: The UNT Digital Library
Video monitoring system for enriched uranium casting furnaces (open access)

Video monitoring system for enriched uranium casting furnaces

A closed-circuit television (CCTV) system was developed to upgrade the remote-viewing capability on two oralloy (highly enriched uranium) casting furnaces in the Y-12 Plant. A silicon vidicon CCTV camera with a remotely controlled lens and infrared filtering was provided to yield a good-quality video presentation of the furnace crucible as the oralloy material is heated from 25 to 1300/sup 0/C. Existing tube-type CCTV monochrome monitors were replaced with solid-state monitors to increase the system reliability.
Date: March 1, 1978
Creator: Turner, P. C.
Object Type: Report
System: The UNT Digital Library
Stress corrosion cracking of uranium--niobium alloys (open access)

Stress corrosion cracking of uranium--niobium alloys

The stress corrosion cracking behavior of U-2/sup 1///sub 4/, 4/sup 1///sub 2/, 6 and 8 wt % Nb alloys was evaluated in laboratory air and in aqueous Cl/sup -/ solutions. Thresholds for crack propagation were obtained in these environments. The data showed that Cl/sup -/ solutions are more deleterious than air environments. Tests were also conducted in pure gases to identify the species in the air responsible for cracking. These data showed the primary stress corrodent is water vapor for the most reactive alloy, U-2/sup 1///sub 4/% Nb, while O/sub 2/ is primarily responsible for cracking in the more corrosion resistant alloys, U-6 and 8% Nb. The 4/sup 1///sub 2/% alloy was found to be susceptible in both H/sub 2/O and O/sub 2/ environments.
Date: March 1, 1978
Creator: Magnani, N.J.
Object Type: Report
System: The UNT Digital Library
Compatibility testing of vitrified waste forms (open access)

Compatibility testing of vitrified waste forms

An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any reactions that occur.
Date: March 6, 1978
Creator: Rankin, W.N.
Object Type: Article
System: The UNT Digital Library
Computer simulation of steady-state performance of air-to-air heat pumps (open access)

Computer simulation of steady-state performance of air-to-air heat pumps

A computer model by which the performance of air-to-air heat pumps can be simulated is described. The intended use of the model is to evaluate analytically the improvements in performance that can be effected by various component improvements. The model is based on a trio of independent simulation programs originated at the Massachusetts Institute of Technology Heat Transfer Laboratory. The three programs have been combined so that user intervention and decision making between major steps of the simulation are unnecessary. The program was further modified by substituting a new compressor model and adding a capillary tube model, both of which are described. Performance predicted by the computer model is shown to be in reasonable agreement with performance data observed in our laboratory. Planned modifications by which the utility of the computer model can be enhanced in the future are described. User instructions and a FORTRAN listing of the program are included.
Date: March 1, 1978
Creator: Ellison, R D & Creswick, F A
Object Type: Report
System: The UNT Digital Library
Hot-ion distribution function in ORMAK, the Oak Ridge Tokamak (open access)

Hot-ion distribution function in ORMAK, the Oak Ridge Tokamak

A distortion of the Maxwellian ion-energy distribution function in tokamak-produced plasmas may be revealed in the spectral-line radiation. We report experimental evidence that (1) a change in the value of Z/sub eff/, (2) delayed gas injection, (3) neutral beam injection, and (4) liner cleaning procedures can alter the profile of the Balmer-..cap alpha.. (6563 A) line of hydrogen. The distortion is analyzed in terms of an effective toroidal-drift velocity, ion-temperature relation.
Date: March 1, 1978
Creator: Neidigh, R.V. & Sigmar, D.J.
Object Type: Report
System: The UNT Digital Library
Estimates of the number of large amplitude gusts (open access)

Estimates of the number of large amplitude gusts

Preliminary estimates are presented of the number of occurrences of large amplitude gusts for use in the design of wind energy conversion systems. Existing turbulence information has been combined with an assumed wind speed distribution to arrive at the estimates. The number of large amplitude gusts per year is treated as a function of the annual mean wind speed and terrain roughness. This treatment is based upon the assumptions that the atmosphere has neutral stability during high winds and that the gustiness is induced by flow over surface roughness elements. Large gusts during thunderstorms and other severe weather phenomena are not treated. The results of the study are presented in tabular form as a function of gust amplitude and hourly average wind speed.
Date: March 1, 1978
Creator: Ramsdell, J.V.
Object Type: Report
System: The UNT Digital Library
Only source of energy (open access)

Only source of energy

Various plants that might play a role in the energy mix of the future are discussed and illustrated. Included among them are the Euphorbias and Guayule. (JGB)
Date: March 22, 1978
Creator: Calvin, G. J. & Calvin, M.
Object Type: Report
System: The UNT Digital Library
Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977 (open access)

Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977

The confinement of nuclear wastes in geologic formations is being considered as a method of permanently disposing of the waste. Laboratory experiments (column infiltration, static absorption, and batch partitioning experiments) were performed with nuclides of Cs, Pu, Np, and Am to examine the migratory characteristics of long-lived radionuclides that could be mobilized by groundwaters infiltrating a nuclear waste repository and the surrounding geologic body. In column infiltration experiments, the positions of peak concentrations of Cs in chalk or shale columns; Pu in limestone; Am in limestone, sandstone, or tuff; and Np in a limestone column did not move when the columns were infiltrated with water. However, fractions of each of the nuclides were seen downstream from the peaks, indicating that there was a large dispersion in the relative migration rates of each of the trace elements in the lithic materials studied. The results of static absorption experiments indicate that Pu and Am are strongly absorbed from solution by the common rocks studied and that their migration relative to ground-water flow is thereby retarded. In addition, the reaction rates of dissolved nuclides with rocks were found to vary considerably in different rock-element systems. Batch partitioning experiments were performed to test whether …
Date: March 1, 1978
Creator: Seitz, M.G.; Rickert, P.G.; Fried, S.M.; Friedman, A.M. & Steindler, M.J.
Object Type: Report
System: The UNT Digital Library
HIVELITE propellant characterization (open access)

HIVELITE propellant characterization

None
Date: March 14, 1975
Creator: Finger, M. & Hayes, B.
Object Type: Report
System: The UNT Digital Library
''Sensing'' the elliptical torus (open access)

''Sensing'' the elliptical torus

A method is given for testing the location of an arbitrary point P=(x,y,z) relative to the toroidal surface generated by rotation of an ellipse (y - y-bar)/sup 2//b/sup 2/ + (z - z-bar)/sup 2//c/sup 2/ = 1, b,c,z-bar > o, about the Y axis. This includes the orientation of P with respect to both the outer and inner surfaces fo the degenerate torus generated by an ellipse with c > z-bar. 2 figures.
Date: March 1, 1978
Creator: Cashwell, E.D. & Everett, C.J.
Object Type: Report
System: The UNT Digital Library
Improved drilling: a part of the energy solution (open access)

Improved drilling: a part of the energy solution

None
Date: March 1, 1975
Creator: Alvis, R.L.
Object Type: Report
System: The UNT Digital Library
Low energy components from charge transfer in neutral beams for fusion (open access)

Low energy components from charge transfer in neutral beams for fusion

The MFTF/TFTR injector system is studied. The LLL double charge exchange system is also studied. The stripping problem in surface-production negative ion systems producing beam energies up to 1000 keV is also investigated. (MOW)
Date: March 1, 1977
Creator: Anderson, O. A.
Object Type: Report
System: The UNT Digital Library
Programmable control system for scanning cylindrical parts (open access)

Programmable control system for scanning cylindrical parts

None
Date: March 14, 1975
Creator: Neal, R. E.
Object Type: Report
System: The UNT Digital Library
Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures (open access)

Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures

Tests of closed-end, internally pressurized, Zircaloy-4 tubing specimens were utilized to develop low strain creep characteristics as a function of time at temperatures in the range of 1475/sup 0/F to 2000/sup 0/F (802/sup 0/C to 1093/sup 0/C) and hoop stresses in the range of 250 to 2500 psi for use in loss-of-coolant accident (LOCA) analyses. The strain rate above the start of the alpha to beta phase transformation region, approximately 1490/sup 0/F (810/sup 0/C), was found to be sensitive to the test procedure (stress-temperature history). This is believed to result from variations in the metallurgical structure. A prediction model is presented which provides a conservative upper bound to the low strain test data provided in this report and reported in the literature.
Date: March 1978
Creator: White, L.S. & Busby, C.C.
Object Type: Report
System: The UNT Digital Library
Cross sections for the /sup 7/Li(n,xn) and /sup 7/Li(n,n'. gamma. ) reactions between 1 and 20 MeV (open access)

Cross sections for the /sup 7/Li(n,xn) and /sup 7/Li(n,n'. gamma. ) reactions between 1 and 20 MeV

Differential cross sections for the production of secondary neutrons and gamma rays from neutron interactions in /sup 7/Li have been measured at 50/sup 0/ and 126/sup 0/ (lab) for incident neutron energies in the range 1 to 20 MeV. An electron linac was used as a white neutron source. Incident neutron energies were determined using time-of-flight techniques for a source-to-sample distance of 48 m. Secondary spectra were determined by analysis of the pulse-height distributions observed in a NE-213 scintillation counter. The results are compared to the current evaluated data file (ENDF/B-IV, MAT 1272).
Date: March 1, 1978
Creator: Morgan, G. L.
Object Type: Report
System: The UNT Digital Library
Computer controlled cartridge case quality assurance inspection system (open access)

Computer controlled cartridge case quality assurance inspection system

None
Date: March 1, 1975
Creator: Compton, M R & Erickson, M D
Object Type: Article
System: The UNT Digital Library
Penn Grade Micellar Displacement project. First annual report, June 1975--June 1976 (open access)

Penn Grade Micellar Displacement project. First annual report, June 1975--June 1976

The main objective of the Penn Grade-ERDA Micellar Displacement Project is to assess and hopefully, demonstrate the feasibility of commercial application of the micellar-polymer process for tertiary oil recovery from a rather large, but relatively ''tight'' section of the Bradford Third Sand. The initial phase of this project involves pertinent core and field injectivity measurements from a freshly drilled well, as a basis for assessing the feasibility of a small demonstration test flood to be performed under Phase II. This report details the work done and results obtained under Phase I (Injectivity Test) completed during the first year of the project. These results, having indicated that the pattern test envisaged under Phase II is indeed feasible, work is now in progress to carry the project to the pattern test phase, in pursuit of project goals.
Date: March 1, 1978
Creator: Danielson, H. H.; Paynter, W. T.; Midkiff, F. R. & Finalle, L. L.
Object Type: Report
System: The UNT Digital Library
Impact of increased coal consumption in the Pacific Northwest (open access)

Impact of increased coal consumption in the Pacific Northwest

The objectives of the National Coal Utilization Assessment are: Identification of the environmental, health and socioeconomic impacts to be expected from the increased use of coal; investigation of mitigation strategies that might be used to manage these impacts; and establishment of working relationships with state and regional agencies and utilities. A number of energy issues were identified in the course of the study. Probably the most significant issues in this region are the siting of coal-fired power plants and the tradeoff in water allocation between energy and agriculture. Choices of coal-fired generation sites and water use determine the level of impacts to air, water, land, terrestrial and aquatic ecosystems, and human health and socioeconomics. Air quality impacts were studied by incorporating current and projected emission inventories into both short-range and long-range air quality diffusion models. Results indicate that annual average ambient air quality standards will not be exceeded at any of the sites. Surface water supplies are more than adequate to meet the needs of new coal-fired generating plants located in the Columbia or Snake River; however, future conflicts could arise with agriculture over allocation of water rights. Water quality impacts would be minimal, even in the delicate estuarine and …
Date: March 1, 1978
Creator: Burnham, J.B. (comp.)
Object Type: Report
System: The UNT Digital Library
Stability of plutonium contaminated sediments in the Miami--Erie Canal. [Mound Facility, Ohio, radioactive effluents monitoring] (open access)

Stability of plutonium contaminated sediments in the Miami--Erie Canal. [Mound Facility, Ohio, radioactive effluents monitoring]

This study was conducted to evaluate the stability of plutonium-contaminated sediment in the Miami-Erie Canal. Correlations were sought to relate concentrations at air sampling stations to plutonium-238 concentrations in air and stack emissions, wind direction, particulate loading, rainfall, and construction activities. There appears to be some impact on airborne concentrations at air sampling stations 122 and 123 from the contaminated sediment in the canal and ponds area. For purposes of this evaluation, it was assumed that the plutonium-238 found in the air samples came from the contaminated sediment in the canal/ponds area. To complete the evaluation of the inhalation pathway, dose calculations were performed using actual airborne concentrations of plutonium-238 measured at sampler 123. The dose equivalent to an individual in that area was calculated for 1 yr and 70 yr. Dose calculations were also performed on potential uptake of contaminated vegetation from that area for 1 yr and 70 yr. This study indicates that, although the contaminated sediments in the canal and pond area appear to contribute to airborne plutonium-238, the observed maximum monthly concentration of plutonium-238 in air is a small fraction of the DOE Radioactivity Concentration Guide (RCG) and the nine-month average concentration of plutonium-238 in air …
Date: March 1, 1978
Creator: Farmer, Billy M. & Carfagno, Daniel G.
Object Type: Report
System: The UNT Digital Library
Logistics models for the transportation of radioactive waste and spent fuel (open access)

Logistics models for the transportation of radioactive waste and spent fuel

Mathematical modeling of the logistics of waste shipment is an effective way to provide input to program planning and long-range waste management. Several logistics models have been developed for use in parametric studies, contingency planning, and management of transportation networks. These models allow the determination of shipping schedules, optimal routes, probable transportation modes, minimal costs, minimal personnel exposure, minimal transportation equipment, etc. Such information will permit OWI to specify waste-receiving rates at various repositories in order to balance work loads, evaluate surge capacity requirements, and estimate projected shipping cask fleets. The programs are tailored to utilize information on the types of wastes being received, location of repositories and waste-generating facilities, shipping distances, time required for a given shipment, availability of equipment, above-ground storage capabilities and locations, projected waste throughput rates, etc. Two basic models have been developed. The Low-Level Waste Model evaluates the optimal transportation policy for shipping waste directly from the source to a final destination without any intermediate stops. The Spent Fuel Logistics Model evaluates the optimal transportation policy for shipping unreprocessed spent fuel from nuclear power plants (1) indirectly, that is, to an Away-From-Reactor (AFR) storage facility, with subsequent transhipment to a repository, or (2) directly to …
Date: March 1, 1978
Creator: Joy, D.S. & Holcomb, B.D.
Object Type: Report
System: The UNT Digital Library
Cementitious yttria products (open access)

Cementitious yttria products

An investigation has been made of the physical properties and formation conditions of cements formed in the yttria/salt/water system. Cementitious binders were of the nominal Y/sub 2/(OH)/sub 5/X.H/sub 2/O type (where X represents the Cl/sup -/ or NO/sub 3//sup -/). An ammonium nitrate-produced yttria cement was shown to be sinterable and was demonstrated to form very refractory castable concretes with zirconia or alumina aggregates.
Date: March 1, 1978
Creator: Holcombe, C. E.
Object Type: Report
System: The UNT Digital Library