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Tests on Models of Nuclear Reactor Elements - Head Losses in Core Sub-Assemblies

Description: Losses have been determined for flow through models of various proposed core sub-assemblies as part of a study of the elements of a nuclear reactor. Six core sections and two? axial blanket sub-assemblies have been compared on the basis of drop in piezometric. head or pressure drop. The core sub-assemblies are composed of an entrance nozzle, a lower axial blanket section, the core section, an upper axial blanket section, and a short section for the handling lug. The four parts of the sub-assemb… more
Date: July 1, 1957
Creator: McNown, J. S.; Yagle, R. A. & Spengos, A.
Item Type: Refine your search to only Report
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Transient Thermal Stresses in Pressure Vessels - Part I: Transient Temperature Distribution - Description of Computer Program

Description: This report describes an IBM 704 Computer program for the calculation of transient temperature distribution in axially symmetric solid or hollow bodies. It is the first part of Transient Thermal Stresses in Pressure Vessels. The present report mainly describes the use of the computer program and gives, for two problems, a comparison between computed and analytically known results. The analysis is reported briefly in this report.
Date: September 12, 1957
Item Type: Refine your search to only Report
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PAR Loop Schedule Review

Description: The status of the overall schedule for design, fabrication, and installation of the component items of the PAR loop experiment in the ORR has been brought up to date and reviewed. This is the first review since the original issue of the schedule
Date: October 16, 1957
Creator: Schaffer, Jr. & W.F.
Item Type: Refine your search to only Report
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An Investigation of the Application of the Gas Generator-Free Turbine Cycle to a Nuclear Powered Aircraft

Description: This study has investigated the feasibility of installing a gas generator-free turbine type power plant in the R3Y aircraft, using a circulating fuel reactor as a power source. Two variations of the cycle were considered. The split flow cycle bleeds high temperature, high pressure air from the gas generator directly to the free turbine in the wing. The through flow cycle partially expands the high temperature, high pressure air through the compressor turbine of the gas generator then directs th… more
Date: August 1, 1957
Creator: Alvis, J. H. & Chessman, S. R.
Item Type: Refine your search to only Report
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Preliminary Outline for Book: Engineering for Nuclear Reactor Fuel Reprocessing

Description: This document outlines a book on the subject of reactor fuel reprocessing that is still in the planning stages, representing the authors' thinking as of the arbitrary cut-off date of October 15, 1957. The subject matter that was intended for inclusion was: special considerations in radiochemical processing; chemical processes and operations; mechanical operations; fluid flow; heat transfer operations; solvent extraction; other mass diffusion operations; instrumentation; auxiliary equipment… more
Date: November 15, 1957
Creator: Long, J. T.; Carter, W. L. & Rom, A. M.
Item Type: Refine your search to only Report
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HIGH TEMPERATURE MODERATOR PROGRAM

Description: The purpose of this memorandum is to outline the high temperature hydride moderator program proposed for the.Metallurgy Division. The objectives of this program are (1) to provide physical and mechanical property data required by the reactor designers, (2) to develop methods for fabricating moderator assemblies, and (3) to devise.and conduct tests to evaluate these· assemblies. The requirements in each of these areas and the work proposed to meet them are outlined.
Date: June 12, 1957
Creator: Hikido, T.
Item Type: Refine your search to only Report
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Comparison of the Corrosion Resistance of Some High-Nickel Content Brazing Alloys to Fuel Compositions 44 and 107

Description: Non-chromium bearing brazing alloys containing large percentages of nickel (89 to 93 wt%) show good corrosion resistance to the NaF-KF-LiF-UF{sub 4} (11.2-41.0- 45.3-2.5 mole %, fuel 107) mixture at 1500{degrees}F under seesaw-test conditions. Corrosive action by fuel 107 was greater than that by NaF-ZrF{sub 4}-UF{sub 4} (53.5-40.0- 6.5 mole %, fuel 44) mixture on nickel-base brazing alloys tested.
Date: October 11, 1957
Creator: Manly, W. D.
Item Type: Refine your search to only Report
open access

PRELIMINARY ANALYSIS OF SUPERCHARGED NUCLEAR RAMJET PROPULSION SYSTEM

Description: A preliminary analysis has been made to compare the performance.of a ceramic ramjet reactor powerplant, such as described in General Electric Report No. XDC-56-5-81, with that of such a powerplant supercharged by a metallic-vapor-cycle compressor jet. Performance at sea level, Mach 2.5 is ·reported for the vapor-cycle compressor jet alone, for the ramjet alone, and for the compressor jet - ramjet combination. Results indicate that adding the compressor-jet as a supercharger for the ramjet provi… more
Date: May 17, 1957
Creator: Boppart, J. A.
Item Type: Refine your search to only Report
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