20 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Superheating reactors."  
Results: 1 - 20
open access

Nuclear Superheat Meeting: September 1959

Description: From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Meeting: October 1960

Description: From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.
Date: November 10, 1960
Creator: Mravca, Andrew E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)

Description: Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience… more
Date: February 1965
Creator: Ianni, P. W.; Fritz, J. R. & Law, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Two-Phase Pressure Losses Quarterly Progress Report: Seventh Quarter, August 12, 1963 - November 11, 1963

Description: Technical report describing that the pressure drop along an annular channel with dimensions D(1) = 0.375 inch; D(2) = 0.875 inch, L = 70 inches. Flow was vertical and upward, and only the internal surface was heated. Subcooled conditions existed at the inlet, with two-phase conditions at the exit. Groups of three radial spacer pins on 18-inch centers along the channel, held the inner surface concentric with the outer surface. The single phase loss coefficient for each spacer group is K(8) = 0.2… more
Date: December 2, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Physics Design of the Mixed Spectrum Critical Assembly

Description: Summary: The Mixed Spectrum Superheater (MSSR) is an integral superheater reactor in which boiling occurs in an annular Boiling Water Reactor section and steam in superheated in an unmoderated fast section in the center. A Mixed Spectrum Critical Assembly (MSCA) to be operated at the Vallecitos Atomic Laboratory has been designed to mock up a 75-150 MWe prototype MSSR. The principal experimental measurements aimed at proving the feasibility of the MSSR concept include power distribution, Dopple… more
Date: August 1963
Creator: Reynolds, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Description: Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows… more
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applications of Strain Cycling Considerations to Superheat Fuel Design

Description: A potential performance limitation of superheat fuel is the susceptibility of the fuel cladding to low cycle fatigue failure. Two simplified analytical methods are presented to estimate the cyclic lifetime of circular superheat fuel cladding. One failure relation is based on a displacement method. The other failure relation is based on a stress method. These relations were compared with data from the literature, and with data involving damage obtained by Reynolds. A recommended design procedur… more
Date: June 1963
Creator: Rieger, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer to Superheated Steam

Description: Abstract: The physical property variation of superheated steam differs sufficiently from most other gases to warrant experimental investigation of heat transfer performance. Results are reported here of measurements made in a uniformly heated circular duct with steam at 1000 psi. The data agree very well with the expression use for design purposes, which is based on information in the literature for heating of other gases as well as steam. This work was a continuation of that performed under … more
Date: May 1963
Creator: Sutherland, W. A. (William Alan), 1931-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators

Description: This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be atta… more
Date: May 31, 1963
Creator: Moen, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Description: Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Description: Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Date: January 1964
Creator: Hanford Atomic Products Operation. N-Reactor Project Section.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen