THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON (open access)

THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON

A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as the reso nant circuit of a self tracking radio frequency amplifier over the frequency range 6.5 to 30 Mc at the 20 cps repetition rate of the synchrotron. Between acceleration cycles it is necessary to program the ferrite to a given magnetic state, near that of maximum radio frequency permeability. (auth)
Date: August 29, 1962
Creator: Rees, G.H.
Object Type: Report
System: The UNT Digital Library
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah (open access)

The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which entry can readily be controlled. Specifications for cargohold dose rates, 0.5 rem/yr at 1/5 full power, are satisfactorily met. Additional data obtained include measurements of special points for comparison with dose rates predicted in design calculations, and an experiment examining the result of loss of water from the Savannah's subreactor shield tanks. Predicted dose rates were conservatively higher than the dose rates measured, and the result of the water-loss experiment showed that even with a total emptying of the tanks a safe condition exists only a few feet from the shield. (auth)
Date: August 29, 1962
Creator: Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Object Type: Report
System: The UNT Digital Library
SOLID STATE DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING AUGUST 31, 1961 (open access)

SOLID STATE DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING AUGUST 31, 1961

Progress in solid state physics is reported on the following topics: theory, metals and alloys, nonmetals, reactor materials, and special projects. Twenty-one separate abstracts were prepared. (M.C.G.)
Date: December 29, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The President's Authority to Conduct the War in Vietnam Without a Declaration of War by the Congress (open access)

The President's Authority to Conduct the War in Vietnam Without a Declaration of War by the Congress

This report analyzes the President's authority to conduct war under the constitution, with and without Congressional approval. Contains a list of pros and cons of President Lyndon B. Johnson conducting war in Vietnam
Date: October 29, 1965
Creator: Leng, Russell J.
Object Type: Report
System: The UNT Digital Library
Precedents of the House of Representatives in Respects to Procedure for Censure or Expulsion, 1966 (open access)

Precedents of the House of Representatives in Respects to Procedure for Censure or Expulsion, 1966

This report contains the procedure and outlines of investigating issues caused by elected officials of government.
Date: December 29, 1966
Creator: Tienken, Robert L.
Object Type: Report
System: The UNT Digital Library
Erroneous Predictions and Negative Comments Concerning Exploration, Territorial Expansion, Scientific and Technological Development; Selected Statements (open access)

Erroneous Predictions and Negative Comments Concerning Exploration, Territorial Expansion, Scientific and Technological Development; Selected Statements

This report documents articles that opposed events, buildings, or inventions that are now historically or modernly important, such as the Louisiana Purchase or the invention of the airplane.
Date: May 29, 1969
Creator: Gamarra, Nancy T.
Object Type: Report
System: The UNT Digital Library
Economic Integration in Latin America: An Annotated Bibliography, 1959-1969 (open access)

Economic Integration in Latin America: An Annotated Bibliography, 1959-1969

This report provides a bibliography of sources related to economic integration in South America which were published between 1959 and 1969.
Date: September 29, 1969
Creator: Billings, Elden E.
Object Type: Report
System: The UNT Digital Library
The National Democratic Party (NPD) in Western Germany: Its Background and Present Status (open access)

The National Democratic Party (NPD) in Western Germany: Its Background and Present Status

This report discusses the history of radical nationalistic movements in Germany and the creation and influence of the National Democratic Party (NDP) in West Germany, a right-wing nationalistic political party.
Date: September 29, 1969
Creator: Fletcher, Patrice A.
Object Type: Report
System: The UNT Digital Library
Fair Trial and Free Press (open access)

Fair Trial and Free Press

This report discusses the two constitutional rights, right to a fair trial and right to fair press, which collides with various degree of intensity and urgency primarily in the area of publicity before and during a criminal trial, and discusses some recent major cases, regulations and some proposed solutions.
Date: November 29, 1968
Creator: Zafren, Daniel Hill
Object Type: Report
System: The UNT Digital Library
HEAD-END TREATMENT OF LOW LEVEL WASTES PRIOR TO FOAM SEPARATION (open access)

HEAD-END TREATMENT OF LOW LEVEL WASTES PRIOR TO FOAM SEPARATION

Calcium-magnesium precipitation apparatus was used to reduce the concentrations of these elements in ORNL tap water, used as a substitute for waste water of low level of radioactivity, prior to strontium removal by foam separation. With and without alkali and flocculator chambers and with a stirred sludge of ratio height to diameter equal to 1/1 to ~4/1, use of 5 x 10/sup -3/ M each of NaOH and Na/sub 2/CO/sub 3/ and 2 ppm Fe/sup 3+/ reduced the dissolved Ca + Mg concentrations to 1 to 2 ppm as calcium. Simultaneously, a strontium DF of 20 to 200 was achieved, and, by adding Grundite clay in the proportion ~0.5 1b/ 1000 gal, a cesium DF of 10 to 40 was achieved. (auth)
Date: May 29, 1962
Creator: Schonfeld, E. & Davis, W. Jr.
Object Type: Report
System: The UNT Digital Library
SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY (open access)

SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Object Type: Report
System: The UNT Digital Library
Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments (open access)

Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a single-filament mass spectrometer is emphasized. (auth)
Date: June 29, 1962
Creator: Goris, P.
Object Type: Report
System: The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL (open access)

ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL

The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. The energy of activation for the corrosion reaction (0.0 volt) is 16.5 kcal/mole; in the electropolishing region (1.0 volt) the activation energy is 7.7 kcal/mole. A broad solvent capability for metallic reactor fuels is offered by the HCl-methanol medium since, in addition to zirconium, stainless steel is also dissolved electrolytically while uranium and aluminum dissolve chemically. Other process implications are discussed. (auth)
Date: December 29, 1961
Creator: Aylward, J. R.; Whitener, E. M. & Hahn, H. T.
Object Type: Report
System: The UNT Digital Library
High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide (open access)

High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide

Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio and the pressure of the two gases. The oxidation reactions proceeded through a selective depletion of chromium from the alloy which increased the carbon solubility and depletion of nickel which led to the transformation of austenite to ferrite. Parabolic reaction rates were observed for the formation of the protective oxides. Arrhenius plots of rate constants versus 1/T indicated the presence of several oxides which was confirmed by other methods. Carburization or decarburization reactions occurred coincidentally with oxidation and depended upon temperature and (P/sub CO/)/sup 2/ /P/sub CO2/ and the P/sub co2//P /sub CO/. Neither was detected below 600 deg C. Between 600--900 deg C, only carburization occurred and appeared to be mainly dependent on the temperature. Above 900 deg C, both carburization and decarburization …
Date: August 29, 1962
Creator: Inouye, H.
Object Type: Report
System: The UNT Digital Library
Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor (open access)

Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor

A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Thermal stresses in the superheater were minimized by designing the annular element so that temperatures are kept as uniform as possible at every axial location. In all cases, sufficient heat dissipation capacity was found to exist to ensure an ample margin of safety. (M.C.G.)
Date: August 29, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
HEXAFLUORIDES OF MOLYBDENUM, TUNGSTEN AND URANIUM. II. REACTIONS WITH LIQUID AND GASEOUS DINITROGEN TETROXIDE (open access)

HEXAFLUORIDES OF MOLYBDENUM, TUNGSTEN AND URANIUM. II. REACTIONS WITH LIQUID AND GASEOUS DINITROGEN TETROXIDE

Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)
Date: January 29, 1962
Creator: Geichman, J. R.; Smith, E. A.; Swaney, L. R. & Ogle, P. R.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1962 (open access)

Chemical Processing Technology Quarterly Progress Report, January-March 1962

The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …
Date: June 29, 1962
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
Waste Treatment and Disposal Progress Report for August and September 1961 (open access)

Waste Treatment and Disposal Progress Report for August and September 1961

Work is being carried out to develop and demonstrate on pilot plant scale integrated processes for treatment and disposal of radmoactive wastes. High-level waste calcination, low-level waste treatment, economic and hazards evaluation, engineering evaluation, disposal in deep wells, disposal in natural salt formations, Clinch River studies, fundamental studies of minerals, and White Oak Creek basin study are discussed. (M.C.G.)
Date: November 29, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Object Type: Report
System: The UNT Digital Library
Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962 (open access)

Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962

The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe …
Date: June 29, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Data Analysis Techniques for Gamma-Ray Scintillation Spectrometry (open access)

Data Analysis Techniques for Gamma-Ray Scintillation Spectrometry

A series of computer programs are described which Were successfully applied to the reduction of pulse-height data using digital computers. Calculations carried out by these programs include: determination of pulse height vs energy response of an NaI detector; calculation of coincidence sum spectra; and the analysis of complex pulse-height spectra to obtain energies and relative intensities of individual gamma rays or relative abundances from a mixture of radionuclides. Measurement problems and instrumental requirements are discussed in detail. (auth)
Date: May 29, 1962
Creator: Heath, R. L.
Object Type: Report
System: The UNT Digital Library
Underground radioactive materials in 100-H and F plants (open access)

Underground radioactive materials in 100-H and F plants

At 100-H Area there are 13 locations and at 100-F Area 16 locations where radioactive material was deposited underground. Five of these locations, 2 at 100-H and 3 at 100-F, have been permanently terminated as burial sites in compliance with Radiation Control Standards. They contain solid waste with significant quantities of long-life radionuclides. Burial locations within the 105 Building exclusion fences were not marked with permanent posts as the exclusion fences are sufficient marking for such sites. Other locations not permanently marked were the components of the effluent systems, including the 107 retention basins, 1904 outfall structures and associated piping. Control objectives for these locations were to prevent contamination spreads and limit personnel access for several years. Similar objectives applied to locations where small quantities of liquid waste were released to ground, or small amounts of surface-contaminated materials were buried. At these locations, existing fences and radiation zone signs were left in place. The permanently posted burial grounds contain two general types of radioactive waste: neutron-activated reactor components, and surface-contaminated material and equipment. The activated components consist almost entirely of steel and aluminum. The most significant radionuclide contained in these materials is 5-year /sup 60/Co. The surface contaminants are primarily …
Date: October 29, 1965
Creator: Herman, G. Jr.
Object Type: Report
System: The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART II. NICHROME IN NITRATE SOLUTIONS (open access)

ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART II. NICHROME IN NITRATE SOLUTIONS

None
Date: December 29, 1961
Creator: Aylward, J. R. & Whitener, E. M.
Object Type: Report
System: The UNT Digital Library
BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1962 throughFebruary 1963 (open access)

BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1962 throughFebruary 1963

This report covers the following titles: (1) A versatile solvent to replace phenol for the paper chromatography of radioactive intermediary metabolites; (2) Chromatography of plant lipids on alumina paper; (3) Quinone and pigment composition of chloroplasts and quantasomes from Spinacea oleracea; (4) The lipid composition of chloroplast lamellae from Spinacea oleracea; (5) Metal chelates and photochemistry of flavins; (6) Photoinduced ESR in some solutions of organic electron donors and acceptors; (7) Fluorescence of oriented dye-macromolecule complexes--Theoretical study; (8) Formation of adenine by electron irradiation of methane, ammonia, and water; (9) Uptake of organic compounds by planarians; (10) The planaria: Absorption spectrum, cell disaggregation, and studies on homogenates.
Date: March 29, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
A Possible Phase Transition in Liquid He3 (open access)

A Possible Phase Transition in Liquid He3

A possible phase transition in liquid He{sup 3} has been investigated theoretically by generalizing the Bardeen, Cooper, and Schrieffer equations for the transition temperature in the manner suggested by Cooper, Mills, and Sessler. The equations are transformed into a form suitable for numerical solution and an expression is given for the transition temperature at which liquid He{sup 3} will change to highly correlated phase. Following a suggestion of Hottelson, it is shown that the phase transition is a consequence of the interaction of particles in relative D-states. The predicted value of the transition temperature depends on the assumed form of the effective single-particle potential and the interaction between He{sup 3} atoms. The most important aspects of the single-particle potential are related to the thermodynamic properties of the liquid just above the transition temperature. Two choices of the two-particle interaction, oonstituent with experiments, yield a second-order transition at a temperature between approximately 0.01 K and 0.1 K. The highly correlated phase should exhibit enhanced fluidity.
Date: January 29, 1960
Creator: Emery, V. J. & Sessler, A. M.
Object Type: Report
System: The UNT Digital Library