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A-11 seven cluster model: FFL-10 solid core tests

Description: This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964
Date: December 18, 1964
Creator: Cherish, P. & Leff, G.J.
Partner: UNT Libraries Government Documents Department
open access

ANALYTICAL CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 15, 1963

Description: Research and development progress is reported on analytical instrumentation, chemical analysis of advanced reactor fuels, analytical studies of molten-salt systems, special research problems, reactor projects, effects of radiation on analytical methods, x-ray and spectrochemical analyses, spectroscopy, optical and electron microscopy, nuclear and radiochemical analyses, inorganic preparations, organic preparations, and analytical development. Service analyses are also described. Separate abstra… more
Date: February 18, 1964
Partner: UNT Libraries Government Documents Department
open access

AXIAL TEMPERATURE AND PRESSURE DISTRIBUTION IN EGCR. DEVELOPMENT OF THE PTD-1 PROGRAM

Description: The equations and procedures of the PTD-1 program for obtaining the surface temperature distribution, the gas bulk temperature, and the pressure distribution for any of the 234 channels in the EGCR are developed. The program, in FORTRAN for the IBM 7090, is designed for any arbitrary power distribution yielding a constant gas outiet temperature or a given maximum surface temperature and includes the effects of thermal radiation on surface and bulk gas temperatures. The flow sheet and some resul… more
Date: February 18, 1964
Creator: Robinson, J.C. & Lence, J.T.
Partner: UNT Libraries Government Documents Department
open access

The Biology of Aging

Description: No Description Available.
Date: March 18, 1964
Creator: Curtis, H. J.
Partner: UNT Libraries Government Documents Department
open access

Cross Sections for Reactor Analysis

Description: A listing of the data on the revised tape is presented. The nuclear data are a reproduction of the computer printout. Other nuclear data (spectra, energy, absorption cross section of some poisons and absorption and fission cross sections of selected fuel materials) were transcribed from the tape listing to provide a more compact format or to allow easier comparison of absorbers and fuels. (auth)
Date: March 18, 1964
Creator: Brunner, J. M. & Henderson, W. B.
Partner: UNT Libraries Government Documents Department
open access

Cryogenic Tensile Properties of Selected Aerospace Materials

Description: Tensile properties data are presented on fifteen materials which were tested at 75°F, -100°F, -320°F, and -425°F temperatures. The test equipment utilized to obtain these data and test methods are described. The test results are discussed.
Date: August 18, 1964
Creator: Weleff, W.; Emmons, W. F. & McQueen, H. S.
Partner: UNT Libraries Government Documents Department
open access

Interim report VII, production test IP-549-A half-plant low alum feed water treatment at F Reactor

Description: A half-plant low alum water treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by the analysis of ledge corrosion attack on fuel elements, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from the normal production fuel irradiated in process water treated with two different alu… more
Date: March 18, 1964
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
open access

Investigation of the Hydraulics of Horizontal Drains in Plumbing Systems

Description: From introduction: "In this paper, data obtained by Hunter and by the author are reported from laboratory investigations of (1) surge flow introduced into empty simply drains, (2) attenuation of surges in simple drains, (3) continuous full-section flow in simple drains under substantially steady, uniform conditions, (4) steady flow in compound drains, and (5) surge flow introduced through a branch drain into the side or top of a main drain carrying steady flow."
Date: December 18, 1964
Creator: Wyly, Robert S.
Partner: UNT Libraries Government Documents Department
open access

IPD production projections

Description: Two changes have been incorporated in the tables of this draft: (1) The lithium-aluminum tonnages required for blanket and E-N loadings have been changed, (2) The production numbers for the small production reactors have been reduced per AEC direction, and a separate table is included for these numbers. Included data are power levels, operating efficiency, exposure, tonnage, conversion ratios, and annual production for the C, K, and small reactors.
Date: July 18, 1964
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
open access

K reactor mixer study aluminum spline tubes

Description: Reference 1 gave mixer recommendations for aluminum spline tubes at the K reactors. On completion of the study, R. F. Corlett requested a more detailed economic study of mixer useage at KW reactor. R. G. Clough also requested additional information on use of mixer elements in fringe tubes. In order to answer these requests, additional information was needed and requested. A. W. Medcalf replied giving enriched metal requirements in support of mixers. No other information vas received so it was n… more
Date: August 18, 1964
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
open access

PT IP-603-I, Evaluation of accidental fuel flushing potential D-DR reactors. Final report

Description: The purpose of Production Test IP-603-I described in this report was to obtain data to help determine if uranium I&E fuel can be flused from tubes set up for discharge on a valved down corssheader by raising the front riser pressure. The test consisted of valving down one header at shutdown riser pressure, then increasing the riser pressure and recording the resulting front nozzle pressures on selected tubes uncapped on the rear. Test results and conclusions are presented.
Date: March 18, 1964
Creator: George, D. K. & Hollifield, P. J.
Partner: UNT Libraries Government Documents Department
open access

Tentative U-233 and thorium nitrate specifications

Description: This report discusses the review of the proposed thorium nitrate specifications,the preparation of tentative product specifications for Purex U-233 and thorium nitrates, and an estimation of the feasibility, cost and product composition for providing U-233 oxide at Hanford. The tentative specifications proposed for U-233 and thorium product for the Purex Plant are presented. The values chosen represent the understanding of feed material and reactor processing needs and the current estimates of … more
Date: December 18, 1964
Creator: Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
open access

THERMAL ANALYSIS OF AN ANODIZED REFLECTOR FOR SNAP-2

Description: Anodization of the SNAP reflector for the 125 kw, 1300 deg F design point results in a reflector temperature of 760 deg F. By comparison the reflector temperature for the 53 kw, 1200 deg F design point with no anodization was 795 deg F. (auth)
Date: February 18, 1964
Creator: Dufoe, G.E.
Partner: UNT Libraries Government Documents Department
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