122 Matching Results

Search Results

Results: 1 - 24 next
open access

Bond Energies, Valence State Energies And Resonance¹,²

Description: Previous attempts to interpret chemical structure in terms of x-electron resonance have been recently criticized. A reinterpretation of the lengths of the C-C bonds in terms of orbital radii has not revealed any effects of x-electron resonance in the ground states of classical molecules such as 1, 3-butadiene, methyl acetylene, etc. Even in a non-classical molecule such as benzene, resonance shortening of the CC bond is only in terms of the strengths of the hybrid orbitals. If the lengths and f… more
Date: February 1961
Creator: Somayajulu, G. R.
Partner: UNT Libraries Government Documents Department
open access

The Infrared Spectra Of Marginally Metallic Systems, Sodium-Ammonia Solutions

Description: The sodium-ammonia solution system permits investigation of an array of compositions spanning the transition from non-metallic to metallic bonding. Reflection spectra in the range 1-20 [ ] were measured for solutions of mole ratio 5.5 to 168 [ ] per Na. The dilute solutions show peaks characteristic of the vibrations of ammonia and a strong peak near 1.5 [ ] which is assigned to the solvated [ ] species. Concentrated solutions show high reflectivity over broad wavelength ranges. The results for… more
Date: February 1961
Creator: Beckman, Tad A., 1936- & Pitzer, Kenneth S. (Kenneth Sanborn), 1914-1997
Partner: UNT Libraries Government Documents Department
open access

Bremsstrahlung

Description: An electron can suffer a very large acceleration in passing through the Coulomb field of a nucleus, and in this interaction the radiant energy (photons) lost by the electrons is called bremsstrahlung (also, bremsstrahlung sometimes designates the interaction itself). If an electron whose total energy [formula] traverses matter of atomic number Z, the electron loses energy chiefly by bremsstrahlung. This case is considered here.
Date: February 1961
Creator: Kenney, R. W.
Partner: UNT Libraries Government Documents Department
open access

Effects Of A Magnetic Field On Natural Convection In A Toroidal Channel

Description: The problem of the natural convection of an electrically and thermally conducting fluid within a long, narrow, vertical toroidal channel centered in a large block of an electrically and thermally conducting solid is analyzed. A uniform horizontal magnetic field is applied to the fluid, and the bottom of the solid block is maintained at a higher fixed temperature than the top. The laminar steady-state single-cell convective motion of the fluid is considered and an approximate solution is found f… more
Date: February 1961
Creator: Concus, Paul
Partner: UNT Libraries Government Documents Department
open access

Orbital Radii, Bond Length And Resonance

Description: The radius of a c-p hybrid orbital has been found to be given by the expression: [formula] where A is the radius of the pure p orbital, B, a universal constant equal to 0.336 A, and [ ], the coefficient of mixing in the hybrid s + [ ]. When radii appropriate for the orbitals that are paired together are used, bond length is additive of the orbital radii and no Schomaker-Stevenson correction is necessary. This shows that most bonds can be treated as covalent, single and localized.
Date: February 1961
Creator: Somayajulu, G. R.
Partner: UNT Libraries Government Documents Department
open access

Kinematics And Dispersion Relations For General Production Processes

Description: The method of dispersion relations has in recent years found a wide application for the study of elementary particle reactions. Most of the work, however, deals with reactions of the type [formula], while the theory of those with more than two particles in the final state is still in a very preliminary stage. One reason for this is that even with only three particles in the final state the theory is already much more complicated. Nevertheless, a further development of the theory seemed to us ve… more
Date: February 2, 1961
Creator: Kretzschmar, Martin
Partner: UNT Libraries Government Documents Department
open access

Utilization of Radiactive Isotpoes in Coal Process Research

Description: "This is the third quarterly report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of accurate low-level tritium assay for tagged hydrocarbons has been resolved and attention is now primarily directed at the questions of tritium mobility and radio-chemical purity in tagged tracers."
Date: February 15, 1961
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
open access

A Partially Degenerate, Relativistic, Ideal Electron Gas

Description: Tables of the electron pressure and kinetic energy for a partially degenerate, relativistic, ideal electron gas are computed by numerical integration using an IBM 7090 electronic calculator. These are given in terms of log10(B) and log10(0), where B is the ratio of the temperature to the rest mass of the electron and (O) is proportional to the numerical density of electrons. The tables include values of T from 5 million to 400 billion degrees and cover the range of electron densities from the r… more
Date: February 23, 1961
Creator: Grasberger, William H.
Partner: UNT Libraries Government Documents Department
open access

Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Description: Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data o… more
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the r… more
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
open access

KW wet critical loading three group flux

Description: A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector … more
Date: February 15, 1961
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
open access

Analytical considerations for K-downcomer and bellows

Description: A free body diagram of the bellows will show the possibility of three forces -- one in each direction, three moments -- one in each plane, and the internal pressure. Any or all of these forces and moments may fluctuate due to variations in a driving force, e.g., separation of streamlines which creates slugging of flow through an elbow. Whereas the static equilibrium condition can be analyzed and stresses and strains computed, the dynamic condition cannot be approached without information on the… more
Date: February 28, 1961
Creator: Lomax, C. C.
Partner: UNT Libraries Government Documents Department
open access

Revised requirements for continuous birch recovery at Redox

Description: The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The rev… more
Date: February 2, 1961
Creator: Barnes, R. G.
Partner: UNT Libraries Government Documents Department
open access

Irradiated uranium fire hazard

Description: Earlier this year we briefly discussed the potential hazard of incurring an inadvertent uranium fuel element fire during discharge. This letter will provide data which will be of assistance to you in assessing the potential hazard, and in establishing charge-discharge procedures to minimize the probability of an irradiated fuel element lodged in the discharge area reaching aluminum jacket melting temperature without detection.
Date: February 16, 1961
Creator: Reid, R. W.
Partner: UNT Libraries Government Documents Department
open access

100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reac… more
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
open access

E-N and blanket conversions from analysis of tubes irradiated at H

Description: A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.
Date: February 10, 1961
Creator: Lang, L. W. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
open access

Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mix… more
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

A standard AlSi braze wetting test for aluminum components used in the lead-dip process

Description: Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting… more
Date: February 1, 1961
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
open access

Radiochemistry for the rupture of a Zircaloy-2 clad uranium fuel element in KER-1

Description: During the 0800--1600 shift on July 7, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 3 and Loop 4 instruments indicating a possible fuel element failure in Loop 1. The KE Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant samples and a thermocouple wire sample… more
Date: February 28, 1961
Creator: Demmitt, T. F.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen