AEC Hot Cells and Related Facilities (open access)

AEC Hot Cells and Related Facilities

Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Date: May 1958
Creator: Fosdick, Ellery R.
Object Type: Report
System: The UNT Digital Library
AEC Hot Cells and Related Facilities (open access)

AEC Hot Cells and Related Facilities

Shielded enclosures equipped with viewing devices and remote-hauling equipment for use in experiments and processes involving radioactivity are referred to as hot cells. The hot cell includes the biological shield enclosing the working space, viewing devices, special ventilating equipment, and special equipment for use in the hot cells, such as manipulators, cranes, machine tools, and measuriag devices. A hot cave is the same as a hot cell. A junior hot cave is a small-sized hot cave. A summary is presented of pertinent data on hot cells in use at various AEC installations. (C.H.)
Date: May 1, 1958
Creator: Fosdick, Ellery R.
Object Type: Report
System: The UNT Digital Library
An approximate analytical method for studying entry into planetary atmospheres (open access)

An approximate analytical method for studying entry into planetary atmospheres

Report presenting a single, ordinary, nonlinear differential equation of second order that can be used for determining entry into an exponential planetary atmosphere. The reduced equation includes various terms, some of which represent the gravity force, the centrifugal acceleration, and the lift force. A number of solutions for lifting and nonlifting vehicles entering at various initial angles are obtained from the complete nonlinear equation.
Date: May 1958
Creator: Chapman, Dean R.
Object Type: Report
System: The UNT Digital Library
Bibliography of Reports Relating to Project Sherwood (Controlled Thermonuclear Reactions) Written at University of California Radiation Laboratory, Livermore and Berkeley : 1953-1957 (open access)

Bibliography of Reports Relating to Project Sherwood (Controlled Thermonuclear Reactions) Written at University of California Radiation Laboratory, Livermore and Berkeley : 1953-1957

"This bibliography is a compilation of titles to unclassified reports, journal articles and conference papers written by members of the University of California Radiation Laboratory, Livermore and Berkeley, relating to Project Sherwood (Controlled Thermonuclear Reactions) from 1953 through 1957."
Date: May 1, 1958
Creator: Frost, Frederick E.
Object Type: Report
System: The UNT Digital Library
Bibliography of Reports Relating to Project Sherwood (Controlled Thermonuclear Reactions) Written at University of California Radiation Laboratory, Livermore and Berkeley-1953 Through 1957-Unclassified Section (open access)

Bibliography of Reports Relating to Project Sherwood (Controlled Thermonuclear Reactions) Written at University of California Radiation Laboratory, Livermore and Berkeley-1953 Through 1957-Unclassified Section

This bibliography is a compilation of titles to unclassified reports, journal articles, and conference papers. The individual papers are divided into sections according to the year in which they appeared. (M.H.R.)
Date: May 1, 1958
Creator: Frost, F.E. comp.
Object Type: Report
System: The UNT Digital Library
Contact-Resistance Symposium, Bendix Aviation Corporation, Kansas City Division, Sandia Corporation, June 14, 1957, Albuquerque, New Mexico (open access)

Contact-Resistance Symposium, Bendix Aviation Corporation, Kansas City Division, Sandia Corporation, June 14, 1957, Albuquerque, New Mexico

The objectives of the conference were to accomplish an interchange of information and study the determination of contact resistance. The effect of contacts on AEC production problems is discussed. Otber discussions are presented one applications of contact devices, present testing criteria, materials and process variables, process controls, and future development plans. (T.R.H.
Date: May 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Cross Section, Volume 4, Number 12, May 1958 (open access)

The Cross Section, Volume 4, Number 12, May 1958

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.
Date: May 1958
Creator: High Plains Underground Water Conservation District No. 1 (Tex.)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Originally issued as S and P 1963A, Parts I and II. A design and feasibility study of a pebble bed reactorsteam power plant is presented, The reactor design which evolved from this study is a 125 Mwe heliumcooled two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Nuclear characteristics, costs, etc., are given. (W.D.M.)
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Dig Reactor Pressure Vessel Specification : Ordering Data (KPE-3023) (open access)

The Dig Reactor Pressure Vessel Specification : Ordering Data (KPE-3023)

The specifications for the D1G reactor pressure vessel and accompanying insulation, shield tank, thermocouples, test heads, fixtures, tools, and repair parts are given- (T-R-H-)
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Distribution of Uranium in Rocks of Pennsylvanian Age in Northeastern Oklahoma, Southeastern Kansas, and Western Missouri (open access)

Distribution of Uranium in Rocks of Pennsylvanian Age in Northeastern Oklahoma, Southeastern Kansas, and Western Missouri

The following report covers investigations on sedimentary rocks of Middle Pennsylvanian age in northeastern Oklahoma, southeastern Kansas, and western Missouri. Distribution of uranium and other trace elements in these rocks was studied during 1955 and 1956.
Date: May 1958
Creator: Danilchik, Walter & Hyden, H. J.
Object Type: Report
System: The UNT Digital Library
Droplet Impingement and Ingestion by Supersonic Nose Inlet in Subsonic Tunnel Conditions (open access)

Droplet Impingement and Ingestion by Supersonic Nose Inlet in Subsonic Tunnel Conditions

"The amount of water in cloud droplet form ingested by a full-scale supersonic nose inlet with conical centerbody was measured in the NACA Lewis icing tunnel. Local and total water impingement rates on the cowl and centerbody surfaces were also obtained. All measurements were made with a dye-tracer technique" (p. 1).
Date: May 1958
Creator: Gelder, Thomas F.
Object Type: Report
System: The UNT Digital Library
Effect of Solvent Degradation on the Purex Process (open access)

Effect of Solvent Degradation on the Purex Process

From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."
Date: May 1958
Creator: Siddall, Thomas H., III; Wallace, Richard M. & Prout, W. E.
Object Type: Report
System: The UNT Digital Library
Effect of Solvent Degradation on the Purex Process (open access)

Effect of Solvent Degradation on the Purex Process

The combined attack of HNO/sub 3/ and HNO/sub 2/ on TBP-kerosene solvents used in the Purex Process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination. (auth)
Date: May 1, 1958
Creator: Siddall, T. H., III & Wallace, R. M.
Object Type: Report
System: The UNT Digital Library
ENGINEERING MATERIALS LIST. A Catalog of Drawings, Photographs, and Specifications Released by the United States Atomic Energy Commission. Supplement 1: SHIPPINGPORT PRESSURIZED WATER REACTOR (open access)

ENGINEERING MATERIALS LIST. A Catalog of Drawings, Photographs, and Specifications Released by the United States Atomic Energy Commission. Supplement 1: SHIPPINGPORT PRESSURIZED WATER REACTOR

Unclassified Engineering Materials List, TM-4100(lst Rev.), is a catalog of available U. S. Atomic Energy Commission unclassified engineering drawing materials on the peaceful applications of atomic energy. The engineering literature described in this publication includes drawing, specifications, photographs, bill of materials, cost analysis, design criteria, psrts lists, and supporting textual data. This consolidated list m- cludes all materials originally announced in TM-4100, January 1957, and TID-4100, Supplement 1, July 1957, and additional engineering data received and cataloged by TlSE after the original issuances. The entire publication, TID-4100 lst Revision Supplement 1, is devoted to the Shippingport Pressurized Water Reactor. (W.L.H.)
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
An experimental investigation of wake effects on hydro-skis (open access)

An experimental investigation of wake effects on hydro-skis

Report presenting an experimental investigation to determine the effects of planing in a wake on the forces of a planing surface and to locate desirable positions in the wake with regard to the lift and lift-drag ratio of the planing surface. Two combinations of hydro-skis were tested: one with two in tandem and one with three arranged with one hydro-ski in the front and two in the back. Results indicated that the rear hydro-ski in tandem arrangement could have large increases in lift coefficient and small improvements in lift-drag ratio compared with the regular configuration.
Date: May 1958
Creator: McBride, Ellis E. & Fisher, Lloyd J.
Object Type: Report
System: The UNT Digital Library
F0010--A TWO-DIMENSIONAL IBM-704 CODE FOR THE CALCULATION OF THERMAL STRESSES IN A LONG, HOLLOW CYLINDER WITH INTERNAL HEAT GENERATION (open access)

F0010--A TWO-DIMENSIONAL IBM-704 CODE FOR THE CALCULATION OF THERMAL STRESSES IN A LONG, HOLLOW CYLINDER WITH INTERNAL HEAT GENERATION

None
Date: May 1, 1958
Creator: Brand, K.W.; Kraus, H. & Lawton, T.J.
Object Type: Report
System: The UNT Digital Library
Flight Investigation of Effects of Retreating-Blade Stall on Bending and Torsional Moments Encountered by a Helicopter Rotor Blade (open access)

Flight Investigation of Effects of Retreating-Blade Stall on Bending and Torsional Moments Encountered by a Helicopter Rotor Blade

Note presenting flight tests conducted with a medium-size single-rotor helicopter, one blade of which was equipped with strain gages, to determine the effects of retreating-blade stall on the rotor blade bending and torsional moments during high-speed flight and pull-up maneuvers. The results indicate that retreating-blade stall has a substantial effect on the periodic rotor blade moments. Results regarding the effect of stall in steady forward flight and effect of stall in pull-up maneuvers are provided.
Date: May 1958
Creator: Ludi, LeRoy H.
Object Type: Report
System: The UNT Digital Library
General solutions for flow past slender cambered wings with swept trailing edges and calculation of additional loading due to control surfaces (open access)

General solutions for flow past slender cambered wings with swept trailing edges and calculation of additional loading due to control surfaces

Report presenting the use of the slender-wing-type analysis to obtain general expressions for the surface pressure, lift, and rolling moment for cambered wings with swept trailing edges. The results are specialized to give the additional loading due to the deflection of trailing-edge control surfaces and the loading due to a particular type of wing twist. A numerical example for aileron control is included.
Date: May 1958
Creator: Klunker, E. B. & Harder, Keith C.
Object Type: Report
System: The UNT Digital Library
Geology and Ore Deposits of the Monument Valley Area, Apache and Navajo Counties, Arizona (open access)

Geology and Ore Deposits of the Monument Valley Area, Apache and Navajo Counties, Arizona

A report about the U. S. Geological Survey's program about uranium investigations and geologic mapping in the Monument Valley area, Arizona. A resource appraisal of the area was an inherent part of the program, and is detailed in this report.
Date: May 1958
Creator: Witkind, I. J. & Thaden, R. E.
Object Type: Report
System: The UNT Digital Library
Health Protection in Beryllium Facilities Summary of Ten Years of Experience (open access)

Health Protection in Beryllium Facilities Summary of Ten Years of Experience

From Introduction: "The purpose of this report is to summarize the information gathered during the design and operation of these facilities so that it may be used in providing for the safe handling of beryllium materials."
Date: May 1, 1958
Creator: Breslin, A. J. & Harris, W. B.
Object Type: Report
System: The UNT Digital Library
IDP physics primer (open access)

IDP physics primer

In this document it is proposed to describe the plant site and to outline the nature of the pile in order to show the specific design and layout requirements for the production of plutonium by nuclear synthesis. The selection of the plant site involved a number of special considerations. An essential requirement was a large dependable supply of relatively pure water that remains at a fairly low temperature throughout the year. A large source of power was required to circulate the tremendous quantities of water. The potential dangers connected with the high energies of the nuclear reaction and the formation of a large quantity of radioactive by- products required large distances between each operating section of the plant, and between the plant and main rail and highway routes. The plant site layout and reactor areas are discussed in the first part of the chapter, followed by a functional description of the more essential pile components. The chapter concludes with a discussion of reactor instrumentation. 24 figs., 2 tabs.
Date: May 1, 1958
Creator: Lockwood, E H
Object Type: Report
System: The UNT Digital Library
Isotopic Purification of Tritium by Electrolysis (open access)

Isotopic Purification of Tritium by Electrolysis

From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."
Date: May 1958
Creator: Johnson, B. S., Jr.; Grace, J. T.; Meyer, L. H.; Karraker, D. G. & Nicholson, C. K.
Object Type: Report
System: The UNT Digital Library