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  Partner: UNT Libraries Government Documents Department
 Resource Type: Report
 Language: English
 Collection: Technical Report Archive and Image Library
Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California

Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California

Date: June 1978
Creator: Argonne National Laboratory
Description: This conference covers various aspects of fossil-fuel power plants based on coal or coal-conversion products, as well as the process control equipment involved in the conversion or combustion processes.
Contributing Partner: UNT Libraries Government Documents Department
An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

Date: 1979?
Creator: Foltman, A. J. & Meneghetti, D.
Description: Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Contributing Partner: UNT Libraries Government Documents Department
Monte Carlo-Based Validation of the ENDF/MC²-II/SDX Cell Homogenization Path

Monte Carlo-Based Validation of the ENDF/MC²-II/SDX Cell Homogenization Path

Date: April 1979
Creator: Wade, D. C.
Description: The results are presented of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC²-II/SDX code sequence is used to transform ENDF/B basic nuclear data into unit cell average broad group cross sections based on the 1D models. Cell average, broad group anisotropic diffusion coefficients are generated using the methods of Benoist or of Gelbard. The resulting broad (approx. 10 to 30) group parameters are used in multigroup diffusion and S(su n) transport calculations of full core XY or RZ models which employ smeared atom densities to represent the contents of the unit cells.
Contributing Partner: UNT Libraries Government Documents Department
ANL/HTP: A Computer Code for the Simulation of Heat Pipe Operation

ANL/HTP: A Computer Code for the Simulation of Heat Pipe Operation

Date: November 1983
Creator: McLennan, G. A.
Description: ANL/HTP is a computer code for the simulation of heat pipe operation, to predict heat pipe performance and temperature distributions during steady state operation. Source and sink temperatures and heat transfer coefficients can be set as input boundary conditions, and varied for parametric studies. Five code options are included to calculate performance for fixed operating conditions, or to vary any one of the four boundary conditions to determine the heat pipe limited performance. The performance limits included are viscous, sonic, entrainment capillary, and boiling, using the best available theories to model these effects. The code has built-in models for a number of wick configurations - open grooves, screen-covered grooves, screen-wrap, and arteries, with provision for expansion. The current version of the code includes the thermophysical properties of sodium as the working fluid in an expandable subroutine. The code-calculated performance agrees quite well with measured experiment data.
Contributing Partner: UNT Libraries Government Documents Department
Physics of Reactor Safety, Quarterly Report: October-December 1977

Physics of Reactor Safety, Quarterly Report: October-December 1977

Date: March 1978
Creator: Argonne National Laboratory. Applied Physics Division.
Description: Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division and Components Technology Division. The work in the Applied Physics Division includes reports on reactor safety program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and Planning of Safety-Related (ZPR) Planning and Experiments Group. Work on reactor core thermal-hydraulic code development performed in the Components Technology Division is also included in this report.
Contributing Partner: UNT Libraries Government Documents Department
Materials Technology for Coal-Conversion Processes Quarterly Report: July-September 1978

Materials Technology for Coal-Conversion Processes Quarterly Report: July-September 1978

Date: 1978
Creator: Ellingson, W. A.
Description: Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding studies on ceramic (refractory) and metallic materials presently being used or intended for use in coal conversion processes. The program entails studies of erosive wear, nondestructive testing, corrosion, refractory degradation, and failure analysis.
Contributing Partner: UNT Libraries Government Documents Department
Development of Lithium/Metal Sulfide Batteries at Argonne National Laboratory: Summary Report for 1977

Development of Lithium/Metal Sulfide Batteries at Argonne National Laboratory: Summary Report for 1977

Date: March 1978
Creator: Nelson, P. A.; Steunenberg, R. K.; Chilenskas, A. A.; Gay, E. C.; Battles, J. E.; Hornstra, F. et al.
Description: This report consists of highlights for 1977 of Argonne National Laboratory's program on the development of lithium/metal sulfide batteries.
Contributing Partner: UNT Libraries Government Documents Department
Analysis of Cracked Core Spray Injection Line Piping from the Quad Cities Units 1 and 2 Boiling Water Reactors

Analysis of Cracked Core Spray Injection Line Piping from the Quad Cities Units 1 and 2 Boiling Water Reactors

Date: December 1983
Creator: Diercks, D. R.
Description: Elbow assemblies and adjacent piping from the loops A and B core spray injection lines of Quad Cities Units 1 and 2 Boiling Water Reactors have been examined in order to determine the nature and causes of coolant leakages and flaw indications detected during hydrostatic tests and subsequent ultrasonic inspections. The elbow assemblies were found to contain multiple intergranular cracks in the weld heat-affected zones. The cracking was predominantly axial in orientation in the forged elbow and wedge components, whereas mixed axial and circumferential cracking was seen in the wrought piping pieces. In at least two instances, axial cracks completely penetrated the circumferential weld joining adjacent components. Based upon the observations made in the present study, the failures were attributed to intergranular stress corrosion cracking caused by the weld-induced sensitized microstructure and residual stresses present; dissolved oxygen in the reactor coolant apparently served as the corrosive species. The predominantly axial orientation of the cracks present in the forged components is believed to be related to the banded microstructure present in these components. The metallographic studies reported are supplemented by x-radiography, chemical analysis and mechanical test results, determinations of the degree of sensitization present, and measurements of weld metal delta ferrite ...
Contributing Partner: UNT Libraries Government Documents Department
Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1977-June 1978

Radiological and Environmental Research Division Annual Report: Part 2, Center for Human Radiobiology, July 1977-June 1978

Date: June 1978
Creator: Rowland, R. E.
Description: Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology.
Contributing Partner: UNT Libraries Government Documents Department
Waste Heat Recovery Fluids for Heavy-Duty Transportation Bottoming Cycle Systems : A Summary Report

Waste Heat Recovery Fluids for Heavy-Duty Transportation Bottoming Cycle Systems : A Summary Report

Date: September 1983
Creator: Krazinski, J. L.; Uherka, K. L.; Holtz, Robert E. & Ash, J. E.
Description: Working fluids used in Rankine bottoming cycle systems for heat recovery from long-haul trucks, marine vessels, and railroad locomotives are examined. Rankine bottoming cycle systems improve fuel economy by converting the exhaust heat from the prime mover into useful power. The report assesses fluid property requirements on the basis of previous experience with bottoming cycle systems. Also, the exhaust gas characteristics for the transportation modes of interest are summarized and compared. Candidate working fluids are discussed with respect to their potential for use in Rankine bottoming cycle systems. Analytical techniques are presented for calculating the thermodynamic properties of single-component working fluids. The resulting equations have been incorporated into a computer code for predicting the performance of Rankine bottoming cycle systems. In evaluating candidate working fluids, the code requires the user to input only a minimal amount of fluid property data.
Contributing Partner: UNT Libraries Government Documents Department
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