States

The adhesion of molten boron oxide to various materials (open access)

The adhesion of molten boron oxide to various materials

This report includes the description and results of an experiment evaluating the amount of adhesion existing between the liquid boron oxide and various materials used in engines.
Date: April 1, 1958
Creator: Witzke, W. R.
Object Type: Report
System: The UNT Digital Library
Alternate Control Rod Materials Silver-Base Alternate Control Rod Alloys (open access)

Alternate Control Rod Materials Silver-Base Alternate Control Rod Alloys

The creep properties of Ag-base alloys and specifically of the Ag-15% In- 5% Cd wrought alloy are presented. (W.L.H.)
Date: April 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Annual Report of the Girl Scouts of the United States of America: 1957 (open access)

Annual Report of the Girl Scouts of the United States of America: 1957

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1957, activities, finance, organizational leadership, and other information about scouting programs.
Date: April 1, 1958
Creator: Girl Scouts of the United States of America
Object Type: Report
System: The Portal to Texas History
Antinucleons (open access)

Antinucleons

The idea of ''antiparticles'', as is well known, originated with Dirac, who in establishing the relativistic equations for the electron noted that besides the solutions corresponding to ordinary electrons there were also ''unwanted solutions'' corresponding to particles of electronic mass but of charge +e instead of the electronic charge - e. The discovery of the positron by CD Anderson offered a brilliant experimental confirmation of Dirac's prediction and gave the first example of an ''antiparticle.''
Date: April 1, 1958
Creator: Segre, Emilio
Object Type: Report
System: The UNT Digital Library
THE ASYMPTOTIC TIME-DEPENDENT TRANSPORT EQUATION (open access)

THE ASYMPTOTIC TIME-DEPENDENT TRANSPORT EQUATION

None
Date: April 1, 1958
Creator: Bengston, J.
Object Type: Report
System: The UNT Digital Library
BEVATRON OPERATION AND DEVELOPMENT. XIII. Period covered February, March, April 1957 (open access)

BEVATRON OPERATION AND DEVELOPMENT. XIII. Period covered February, March, April 1957

During this entire quarter, the Bevatron was shut down for major rework of the magnet-coil air shroud and for the scheduled construction of a new experimental area at the north straight section. The existing west and northwest experimental areas were also improved. The Bevatron motor-generator sets and associated ignitrons were overhauled. At the end of this period, the magnet coil rework is concluded and the scheduled shutdown work is well advanced. (auth)
Date: April 1, 1958
Creator: Hartsough, W. & Salsig, W.
Object Type: Report
System: The UNT Digital Library
Creep of Columbium in a High Fast Neutron Flux Field (open access)

Creep of Columbium in a High Fast Neutron Flux Field

The purpose of this report is to examine the theory of radiation damage to obtain an idea of the extent of this damage.
Date: April 1, 1958
Creator: Gregory, D. P.
Object Type: Report
System: The UNT Digital Library
DIGITAL DATA GATHERING SYSTEM, BLOWDOWN WIND TUNNEL (open access)

DIGITAL DATA GATHERING SYSTEM, BLOWDOWN WIND TUNNEL

Presented at ihe Ninth Meeting of the Supersonic Wind-Tunnel Assoc., Univ. of Southern Calif., and U. S. Naval Air Missile Test Center, Point Mugu, Calif., Apr. The Sandia 12 x 12-inch, transonic, blowdown tunnel facility is being equipped with a 10-channel digital datagathering system. The design and operation of ihe system are discussed. (W.J.H.)
Date: April 1, 1958
Creator: Botner, W T
Object Type: Report
System: The UNT Digital Library
Dilution of liquid oxygen when nitrogen is used for pressurization (open access)

Dilution of liquid oxygen when nitrogen is used for pressurization

Report presenting a graphic method for determining the composition and phases within a propellant tank when liquid oxygen is pressurized with nitrogen gas and some of the calculations involved. The assumed limiting conditions are that pressurizing gas flows adiabatically from the pressure tank and that equilibrium exists in the oxygen-nitrogen system. The experiment indicates that a series dilution of the oxidant occurs when nitrogen is used as a pressurizing gas, but a barrier at the liquid-gas interface would permit the use of nitrogen.
Date: April 1, 1958
Creator: Walsh, Thomas J.; Hibbard, R. R. & Ordin, Paul M.
Object Type: Report
System: The UNT Digital Library
Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office

Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date: April 1, 1958
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type: Report
System: The UNT Digital Library
Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type: Report
System: The UNT Digital Library
FISSION GAS HOLDUP TESTS ON HRT CHARCOAL BEDS (open access)

FISSION GAS HOLDUP TESTS ON HRT CHARCOAL BEDS

Fission gas holdup tests on the HRT charcoal beds under simulated operating conditions are complete. A radioactive tracer technique developed for use in laboratory absorption studies was utilized. The efficiency of the charcoal beds, in regard to holdup of fission gases, exceeds design specifications. On the basis of these tests, the charcoal beds should perform satisfactorily with the l#T operating at 10 Mw with a total oxygen flow of 3 liters/min. or at 5 Mw with a total oxygen flow of 3.5 liters/min., assuming that the maximum charcoal temperature in the first sections of the bed does not exceed 100 deg C and that the temperature in the 6 inch diameter section is in the 15 to 20 deg C range. (auth)
Date: April 1, 1958
Creator: Adams, R. E. & Browning, W. E.
Object Type: Report
System: The UNT Digital Library
FREQUENCY RESPONSE ANALYSIS OF THE HRT FEEDWATER CONTROL SYSTEM (open access)

FREQUENCY RESPONSE ANALYSIS OF THE HRT FEEDWATER CONTROL SYSTEM

A frequency response analysis is made of the HRT fuel feedwater system. The characteristics of the components are determined and used in the differential equation of the system. Using frequency response techniques, theoretical calculations of static and dynamic response characteristics are made for reactor operation at 5 Mw. The conclusions arrived at as a result of this analysis include suggestions for improving the present operation. (auth)
Date: April 1, 1958
Creator: Ball, S.J.
Object Type: Report
System: The UNT Digital Library
HYDRODYNAMIC AND HYDROSTATIC LUBRICATED BEARINGS WITH PARTICULAR REFERENCE TO AIR BEARINGS: A LITERATURE SURVEY (open access)

HYDRODYNAMIC AND HYDROSTATIC LUBRICATED BEARINGS WITH PARTICULAR REFERENCE TO AIR BEARINGS: A LITERATURE SURVEY

S>A search of the unclassified literature and General Eleciric reporis has been made with reference to the use of air as the lubricating fluid in hydrostatic and hydrodynamic bearing applications. (auth)
Date: April 1, 1958
Creator: Koenders, M.A.
Object Type: Report
System: The UNT Digital Library
The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 1: Summary Report (open access)

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 1: Summary Report

Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.
Date: April 1, 1958
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 2: Plant Design (open access)

The Oak Ridge National Laboratory Gas-Cooled Reactor, Part 2: Plant Design

Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.
Date: April 1, 1958
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office (open access)

Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office

Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
Date: April 1, 1958
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
PRELIMINARY REPORT OF FUSED SALT MIXTURE NO. 130 HEAT TRANSFER COEFFICIENT TEST (open access)

PRELIMINARY REPORT OF FUSED SALT MIXTURE NO. 130 HEAT TRANSFER COEFFICIENT TEST

Heat transfer data are presented over a Reyuolds Number range of 400 to 8000 for the test fused salt Mixture No. 130 (62 mol % LiF-37 mol % BeFi-1 mol % UF/sub 4/ for a calibrating used salt Mixture No. 30 (50 mol % NaF--46 mol % ZrF/ sub 4/--4 mol % UF/sub 4/) flowing inside round heat exchanger tubes. A prelima- nary equation is developed for predicting shell-side heat transfer coefficients for liquid metal in turbulent, longitudinal flow over a square tube array having a pitch/diameter ratio of 1.165. An experimental value of the specific heat of fused salt Mixture No. 130 is also determined from the test data. (auth)
Date: April 1, 1958
Creator: Amos, J.C.; MacPherson, R.E. & Senn, R.L.
Object Type: Report
System: The UNT Digital Library
PROCESS DEVELOPMENT QUARTERLY REPORT. PART I. LABORATORY WORK (open access)

PROCESS DEVELOPMENT QUARTERLY REPORT. PART I. LABORATORY WORK

None
Date: April 1, 1958
Creator: Elliott, B. ed.
Object Type: Report
System: The UNT Digital Library
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1958 (open access)

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1958

The thermal conductivity and electrical resistivity of U encapsulated in Zircaloy-2 with NaK as a heat transfer material were determined prior to irradiation. The short-time rupture strength of 15% cold-worked Zircaloy-2 at 290, 345, and 4OO C is reported. Tests to develop the right-angle method of extrusion cladding of U with Al were continued. Pressure bonding of Al to Niplated U by temperature and gas-pressure tecchniques has produced sound metallurgical bonds. A series of 17 alloy compositions was prepared for corrosion testing in an effort to develop a natural-uranium fuel alloy with improved corrosion resistance. A stsdy of the oxidation of U0/sub 2/ was continued. The corrosion of stainless steel by chloride-contaminated nitric acid solutions is reported. Studies are reported on the solidification of unalloyed U ingots. A study of the reactions that may occur during the induction melting of U is reported. Specimens of enriched UN or UC dispersed in stainless steel and clad with stainless steel were investigated to determine tensile properties at elevated temperatures and resistance to irradiation damage. Electrical resistivity and tensile strength measurements were made on U0/sub 2/ stainless steel cermets at room temperatures. Work has continued on the investigation of hydrides of U-Zr alloys …
Date: April 1, 1958
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Object Type: Report
System: The UNT Digital Library
RESIN ATTRITION (open access)

RESIN ATTRITION

ABS>Uranium metal is produced by the bomb reduction of UF/sub 4/ with Mg. The slag from this reduction contains appreciable quantities of U, either in the metallic or the tetrafluoride form, in addition to the MgF/sub 2/. A process for recovering low enrichmeat U from this slag has gone into operation. A study of the causes of resin attrition and their relative magnitude both from an over-all point of view and with specific reference to the Higgins' Column and Dowex 21K resin is preseated. Equipment was designed, assembled, and tested to investigate the effects of valve action, wall to resin and resin to resin friction, repeated chemical cycling, and column height. Certain mechanical properties of the resin beads were investigated, and some existing plant data were analyzed. A discussion of the probable mechanism of attrition and its contribution to the overall amount of attrition is presented. (W.L.H.)
Date: April 1, 1958
Creator: Seiler, G. R.; Ammann, P. R. & Newey, A. B.
Object Type: Report
System: The UNT Digital Library
REVIEW OF HRT FEEDWATER CONTROL SYSTEM (open access)

REVIEW OF HRT FEEDWATER CONTROL SYSTEM

The HRT feedwater control system was reviewed to determine adequacy of the present controls and to evaluate alternate systems as to feasibility and desirability. Results indicate that the present system is adequate for operation from one to five megawatts, but that trouble may be experienced below one megawatt and above five megawatts. Recommendations for improving operations of the present system are presented. Alternate systems of feedwater control are discussed. (auth)
Date: April 1, 1958
Creator: Moore, R.L.
Object Type: Report
System: The UNT Digital Library
Rover conference, week of 17 March 1968, Aerojet-General Corp. (open access)

Rover conference, week of 17 March 1968, Aerojet-General Corp.

None
Date: April 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library