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  Partner: UNT Libraries Government Documents Department
 Decade: 1970-1979
 Year: 1977
 Collection: Technical Report Archive and Image Library
Advanced Fuel Cell Development Progress Report: April-June 1977

Advanced Fuel Cell Development Progress Report: April-June 1977

Date: August 1977
Creator: Ackerman, J. P.; Pierce, R. D.; Nelson, P. A. & Arons, R. M.
Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities directed toward understanding and improvement of molten-carbonate-electrolyte fuel cells operating at temperatures near 923 Kelvin.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Fuel Cell Development Progress Report: January-March 1978

Advanced Fuel Cell Development Progress Report: January-March 1978

Date: 1977?
Creator: Ackerman, J. P.; Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A.; Arons, R. M.; Kinoshita, K. et al.
Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes the development of electrolyte structures which have good electrolyte retention and mechanical properties as well as long term stability, and on developing methods of synthesis amenable to mass production.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Fuel Cell Development Progress Report: July-September 1977

Advanced Fuel Cell Development Progress Report: July-September 1977

Date: November 1977
Creator: Ackerman, J. P.; Pierce, R. D.; Nelson, P. A.; Arons, R. M.; Kinoshita, K.; Sim, J. W. et al.
Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL).
Contributing Partner: UNT Libraries Government Documents Department
Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Date: September 1977
Creator: Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R. & King, M. J.
Description: The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The overall objective of this study is to shed light on any large differences in the long-term potential that exist between various alternative reactor/fuel cycle deployment strategies.
Contributing Partner: UNT Libraries Government Documents Department
Analysis of EBR-II Low-Power Dosimetry Run 78C

Analysis of EBR-II Low-Power Dosimetry Run 78C

Date: December 1977
Creator: Franklin, F. C.; Ebersole, E. R. & Heinrich, R. R.
Description: This report compares calculated reaction rates based on neutron-transport calculations in RZ and XY geometries with measured values from a low-power dosimetry test in EBR-II. Axial distributions of Uranium-235 and uranium-238 fission rates and uranium-238 capture rate are given for various radial locations along the length of the core and the axial reflectors, and along the length of the radial steel reflectors. Reaction rates, primarily at the reactor midplane, are given for a number of fission and capture reactions. The analytical RZ- and XY-geometry models used for the neutronics calculations are described.
Contributing Partner: UNT Libraries Government Documents Department
An Analysis of the High-Temperature Particulate Collection Problem

An Analysis of the High-Temperature Particulate Collection Problem

Date: October 1977
Creator: Razgaitis, Richard
Description: Particulate agglomeration and separation at high temperatures and pressures are examined, with particular emphasis on the unique features of the direct-cycle application of fluidized-bed combustion. The basic long-range mechanisms of aerosol separation are examined, and the effects of high temperature and high pressure on usable collection techniques are assessed. Primary emphasis is placed on those avenues that are not currently attracting widespread research. The high-temperature, particulate-collection problem is surveyed, together with the peculiar requirements associated with operation of turbines with particulate-bearing gas streams.
Contributing Partner: UNT Libraries Government Documents Department
Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II

Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II

Date: November 1977
Creator: Price, C. C.; Sackett, J. I.; Curran, R. N.; Livengood, C. L.; Kehler, P. & Forster, G. A.
Description: This report describes the pulsed-neutron-activation (PNA) flow-measuring technique as applied to in situ fluid-flow measurement at EBR-II. Analytic relationships are derived for modeling the process and estimating the uncertainty in measurement. Results from measurements of both water flow and secondary-sodium flow are presented. Results from PNA measurements of water side of the EBR-II steam system have led better definition of plant parameters. Results from sodium-flow measurements are used to provide a correlation for in situ calibration of the electromagnetic sodium flowmeter in the secondary system.
Contributing Partner: UNT Libraries Government Documents Department
Autoradiographic Technique for Rapid Inventory of Plutonium-Containing Fast Critical Assembly Fuel

Autoradiographic Technique for Rapid Inventory of Plutonium-Containing Fast Critical Assembly Fuel

Date: October 1977
Creator: Brumbach, S. B. & Perry, R. B.
Description: A nondestructive autoradiographic technique is described which can provide a verification of the piece count and the plutonium content of plutonium-containing fuel elements. This technique uses the spontaneously emitted gamma rays from plutonium to form images of fuel elements on photographic film. Autoradiography has the advantage of providing an inventory verification without the opening of containers or the handling of fuel elements. Missing fuel elements, substitution of nonradioactive material, and substitution of elements of different size are detectable. Results are presented for fuel elements in various storage configurations and for fuel elements contained in a fast critical assembly.
Contributing Partner: UNT Libraries Government Documents Department
Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)

Date: November 1977
Creator: Yaggee, F. L.; Purohit, A.; Grajek, W. J. & Poeppel, R. B.
Description: Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
Contributing Partner: UNT Libraries Government Documents Department
Bilinear Cyclic Stress-Strain Analysis for Incoloy 800

Bilinear Cyclic Stress-Strain Analysis for Incoloy 800

Date: 1977?
Creator: Maiya, P. S.
Description: This report describes the bilinear stress-strain analysis under cyclic loading conditions for the alloy Incoloy 800. Although the method for determining the bilinear stress-strain parameters is based on a procedure proposed in the RDT Standard F9-1 for inelastic analysis of Fast Flux Test Facility (FFTF) components, the accuracy and consistency of results have been improved by an analytical technique, which also resulted in certain simplifications. The bilinear stress-strain parameters of solution-annealed Incoloy 800 (Heat HH7058A) under cyclic loading conditions at a strain rate of 8.6 x 10⁻⁵ s⁻¹, total strain range of 0.2 to 0.8 percent, and temperatures of room temperature to 593 degrees C (1100 degrees F) have been determined. The dependence of bilinear parameters on temperature and strain is discussed. The cyclic-hardening characteristics based on correlation of yield parameter k with accumulated plastic strain are also presented.
Contributing Partner: UNT Libraries Government Documents Department
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