UNT Libraries Government Documents Department - 114 Matching Results

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Aging of Al-Li Alloys - Part I

Description: Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) … more
Date: January 1959
Creator: Angerman, C. L.
open access

Canning Graphite for Gas-Cooled Reactors

Description: A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen--oxygen atmosphere. Fabrication techniques for cladding bare and copper--plated graphite cores either in Type 316 stainless steel or Inconel X were developed. Specimens of the various combinations of core and cladding materials were subjected to simulatedservice conditions and evaluated. In all cases the Type 316 stainless steel-clad specimens failed by … more
Date: January 1, 1959
Creator: Paprocki, S. J.; Carlson, R. J. & Bonnell, P. H.
open access

Chemical Processing Department Control Study: Final report on the control of CPD product materials

Description: The purpose of this report is to present the conclusions and recommendations obtained during the course of the CPD Control Study and the conceptual framework upon which they are based. Primary emphasis has been given to the control of product materials. In order to logically present the background for the definition and delineation of an appropriate CPD Control System, Section III of this report discusses a control system in the following manner; (1) the description of the control system inform… more
Date: January 5, 1959
Creator: Shepard, D. F.; Hough, C. G.; Burke, R. C. & Stewart, K. B.
open access

Chemical Processing Department Monthly Report: December 1958

Description: This report for December 1958, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date: January 21, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
open access

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

Description: A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A… more
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
open access

Comparative Costs Of Sea Disposal And Land Burial For The Radioactive Wastes Of The Lawrence Radiation Laboratory

Description: This report is a comparative cost study of radioactive waste disposal for the Lawrence Radiation Laboratory (UCRL). In particular, it compares the costs of sea disposal in depths of 1000 fathoms and of 2000 fathoms off the California coast with land burial of the wastes at the Hanford Atomic Products Operation (HAPO), Richland, Washington, at the National Reactor Testing Station (NRTS), Idaho Falls, Idaho, or at the Nevada Test Site (NTS), Nevada. In the comparison, the cost of utilizing a comm… more
Date: January 21, 1959
Creator: Nielsen, Elmer
open access

Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
open access

Control of Thorium Oxide Particle Size

Description: By carefully controlling the agitation, temperature, concentrations, and reagent addition rate, it was possible to produce a thorium oxide product within 0.3 mu of any selected size between 2.0 and 3.0 mu . The rate of addition of oxalic acid to a thorium nitrate solution was the variable used in the current series of tests. (auth)
Date: January 22, 1959
Creator: Johnsson, K. O. & Ellison, C. V.
open access

Core Characteristics of Four Army Package Power Reactors

Description: A brief discussion of the core charteristics of four uranium fuel, pressurized-water type: Army Package Power Reactors, the SM-1, SM-1A, PM-2A, and SW-2, is presented. The characteristics discussed are cell geometry, fuel plates, core geometry, flux distributions, core loading, core burnout, and control reds. Tables and illustrations are included. (auth)
Date: January 1, 1959
Creator: Gallagher, J. G.; Leibson, M. J. & Byrne, B. J.
open access

Creep Rupture in the Presence of a Fast Neutron Flux

Description: Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
open access

DARED-1--AN IBM-704 PROGRAM FOR REDUCING DATA FROM FOIL IRRADIATION AND FITTING BY LEAST SQUARES TO BESSEL J$sub 0$ OR COSINE FUNCTION

Description: A description is given of a code for the IBM-704 computer which reduces and fits by least squares the measurements of radioactivity of a sequence of foils. Corrections for background, counter deadtime, foil weight, and radioactive decay are applied, and readings outside a specified range are rejected. Errors due to statistical fluctuations are computed and off-center ordinates are calculated. Reduced data are then fitted by least squares to the best value of the arguments of Bessel J/sub o/ or … more
Date: January 1, 1959
Creator: Jedruch, J. & Saalbach, C.
open access

The Decontamination of Reactor Cooling Water with Aluminum

Description: The discharge of cooling water from the Hanford reactors introduce radioactive contaminants to the Columbia River. These materials may subsequently bring about exposure to human populations either through the direct use of the water for sanitary purposes or transfers of the radioisotopes into the food chains. It is therefore desirable to keep to a minimum the amounts of radioisotopes released to the river.
Date: January 28, 1959
Creator: Silker, W. B.
open access

The Design and Uses of High Flux Research and Test Reactors

Description: The need for thermal and fast neutron fluxes in the range of 1 to 5 x l0/ sup 15/ neutrons/cm/sup 2/(sec) for the production of heavy elements such as Cf/ sup 252/ and other special isotopes and for improving the quality of beam experiments, reactor materials testing work, and solid state research has led to plans for the construction of three ultra high flux research reactors. The designs of these and other high flux research reactors are based on the general technology of enriched tank-type r… more
Date: January 1, 1959
Creator: Lane, J. A.
open access

Design Bases for ICPP Waste Calcination Facility

Description: Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
open access

DETECTION OF ThO$sub 2$ CONTAMINATION IN SIMULATED CUTS AND ABRASIONS

Description: Tests have been made to determine the sensitivity of various radiation detection instruments for known amounts of ThO/sub 2/ contained in simulated cuts and abrasions. A shielded Geiger-Mueller counter tube can be expected to detect at least 0.1 mg ThO/sub 2/ when counting for a reasonable length of time provided the ThO/sub 2/ deposit is on the surface of the subject being counted. A shielded gamma-spectrometer-crystal, set at a 50-kev cutoff, can be expected to detect at least 0.5 mg ThO/sub … more
Date: January 15, 1959
Creator: Thomas, D. G. & Hilyer, J. V.
open access

DETERMINATION OF MAXIMUM PERMISSIBLE LEAKAGE FROM THE HRT PROCESS STEAM SYSTEM

Description: Calculations were made to determine the radiation hazard to HRT personnel as a result of leakage to the atmosphere from the process steam system in the event of a heat exchanger tube rupture. These calculations show that with the present four-minute delay before dumping approximately 1020 lb of fuel solution may be transferred to the steam system. The radiation hazard from fission products in the atomosphere will be negligble if the steam killer blower is operating. If this blower is not operat… more
Date: January 30, 1959
Creator: Gift, E.H.
open access

Developments in the HLO Bearing Test Program Interim Report

Description: The chemical processing industry relies heavily on the use of rotary pumps to move massive quantities of liquids. The rotating elements of these pumps, generally of the deep-well turbine type, are submerged in the solution being pumped. This singular factor sometimes imposes a severe limitation on the choice bearings because the liquids are frequently corrosive and have poor lubricity. At the Hanford Atomic Products Operation a further complication arises from the effects of radioactivity in th… more
Date: January 9, 1959
Creator: Wirta, R. W.
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