Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: July 1, 1962
Creator: Rider, B. F.
Object Type: Report
System: The UNT Digital Library
Analysis of Electric Energy Usage in Air Force Houses Equipped with Air-to-Air Heat Pumps (open access)

Analysis of Electric Energy Usage in Air Force Houses Equipped with Air-to-Air Heat Pumps

From Introduction: "One part of this study, which is presented in this Monograph, consists of an analysis of electric energy usage and electric power demand data obtained from a sample group of occupied houses at Little Rock Air Force Base in Arkansas, equipped with heat pumps, water heaters, cooking ranges, clothes dryers, and miscellaneous appliances all operated by electricity."
Date: July 13, 1962
Creator: Achenbach, Paul R.; Davis, Joseph C. & Smith, William T.
Object Type: Report
System: The UNT Digital Library
The Application of an Operational Reactivity Accounting System Based on One-Group Diffusion Theory (open access)

The Application of an Operational Reactivity Accounting System Based on One-Group Diffusion Theory

HW-70780, {open_quotes}An Operational Reactivity Accounting System Based on One-Group Diffusion Theory{close_quotes} describes a reactivity accounting system which is an improvement over the present {open_quotes}flux-squared weighting{close_quotes} system. Several changes and additions have been made which will simplify and increase the accuracy of the system described in the parent document. The changes occur primarily in the application of the system and are compatible with diffusion theory and the parent document. Each change will be described briefly and to illustrate their application an example reactivity balance, using the reactivity accounting system, will be performed.
Date: July 2, 1962
Creator: Stewart, S. L.
Object Type: Report
System: The UNT Digital Library
APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES (open access)

APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES

Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)
Date: July 30, 1962
Creator: Wimmer, R.E.
Object Type: Report
System: The UNT Digital Library
Atom Arrangements in Some Iron-Aluminum Solutions, Report No. 1 (open access)

Atom Arrangements in Some Iron-Aluminum Solutions, Report No. 1

"Short-range order coefficients were measured at 300 and 400°C for iron-aluminum alloys containing 14.8, 18.2, and 20.0 atomic per cent aluminum. These alloys exhibited a strong preference for unlike near neighbors. The short-range order was greater at the lower temperature and increased as the Fe 3Al composition was approached."
Date: July 12, 1962
Creator: Houska, C. R. & Averbach, B. L.
Object Type: Report
System: The UNT Digital Library
Carbide Cathode Studies, Physical and Chemical Redeposition. Quarterly Progress Report, April 1, 1962-June 30, 1962 (open access)

Carbide Cathode Studies, Physical and Chemical Redeposition. Quarterly Progress Report, April 1, 1962-June 30, 1962

The utilization of physical and chemical processes to reduce the rate of vapor loss of thermionic emitters composed of mixed carbides of U and Zr in order to increase the permissible operating temperature is being studied. Preliminary, qualitative results obtained from study of physical redeposition processes showed that increasing the collector temperature may markedly reduce the rate of weight loss from a UC emitter operating at 2053 deg K. The requisite experimental equipment for studies of chemical transport processes was designed and constructed. Experiments will proceed through both a physical chemistry approach to an understanding of the transport processes and a technique to evaluate the efficacy of possible combinations of chemical species by monitoring the electron emission from diodes containing such mixtures. (auth)
Date: July 18, 1962
Creator: Weinberg, A. F.; Yang, L. & Langer, S.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Department Monthly Report: June 1962 (open access)

Chemical Processing Department Monthly Report: June 1962

This report, for June 1962 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; employee relations; and safety and security.
Date: July 20, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Object Type: Report
System: The UNT Digital Library
Cloud Interpretation from Satellite Altitudes (open access)

Cloud Interpretation from Satellite Altitudes

This report is an incomplete study of cloud interpretations from pictures taken by satellite cameras. This study commenced in the Spring of 1960 immediately after the launch of TIROS I.
Date: July 1962
Creator: Conover, John H.
Object Type: Report
System: The UNT Digital Library
Command Links. Volume 1, Section 4 (open access)

Command Links. Volume 1, Section 4

This report addresses command links.
Date: July 24, 1962
Creator: Wilker, L. B.
Object Type: Report
System: The UNT Digital Library
A Computer Program for Calculating One-Dimensional Hydrodynamic Flow: KO Code (open access)

A Computer Program for Calculating One-Dimensional Hydrodynamic Flow: KO Code

A computer program is described for the solution of shock, detonation, and spall problems for one-dimensional linear, cylindrical, or spherical hydrodynamic flow. The Flume option is used for calculating flow- through arbitrary cross sections. (R.J.S.)
Date: July 2, 1962
Creator: Wilkins, M.; French, J. & Giroux, R.
Object Type: Report
System: The UNT Digital Library
Correlation between heat capacity anomaly in Tb and magnetic transition in Tb{sub 2}O{sub 3} (open access)

Correlation between heat capacity anomaly in Tb and magnetic transition in Tb{sub 2}O{sub 3}

None
Date: July 19, 1962
Creator: Gerstein, B. C. & Jelinek, F. J.
Object Type: Report
System: The UNT Digital Library
Correlation of Critical Mass Data on Light Water Moderated, Fully Enriched Uranium, Stainless Steel Reactors. Part 1 (open access)

Correlation of Critical Mass Data on Light Water Moderated, Fully Enriched Uranium, Stainless Steel Reactors. Part 1

Experimental data were collected on over 70 light water moderated, fully enriched uranium, stainless steel, critical cores. An equation for the critical mass of cores with a buckling of 0.007 cm/sup -2/ that is lineally dependent on stainless steel volume fraction and grams of B/sup 10/ was compared with available critical experiments and found to yield reasonable results. A correlation method, relating buckling to ( xi SIGMA /sub s// SIGMA /sub a/) was found to fit the available experiments. (auth)
Date: July 17, 1962
Creator: Lee, D. H.
Object Type: Report
System: The UNT Digital Library
Corrosion Mechanism of Zirconium and Its Alloys--Diffusion of Oxygen in Zirconium Dioxide (open access)

Corrosion Mechanism of Zirconium and Its Alloys--Diffusion of Oxygen in Zirconium Dioxide

The diffusion rate of O in anion-deficient zirconia, ZrO/sub 1.994/, was determined by the interface migration of stoichiometric oxide and is represented by the equation D = 0.055 exp (--33,400 surface proces 3100/RT). A comparison was made with other processes that occur in the metal and the oxide. Excellent agreement was noted between activation energies of O diffusion in ZrO/sub 1.944/ and those for parabolic or cubic oxidation in both air and water. It appears that O diffusion in the oxide is rate-controlling during oxidation of the metal. The corrosion and oxidation behavior of Zr and some alloys are discussed in terms of the oxide defect structure and the electric conductivity behavior in the oxide. A speculative mechanism for corrosion transition to linear rates was suggested on the basis of preferential oxidation of a grain boundary metallic phase. The nature of the phase and of its formation and elimination are discussed. (auth)
Date: July 27, 1962
Creator: Douglass, D. L.
Object Type: Report
System: The UNT Digital Library
The Cross Section, Volume 9, Number 2, July 1962 (open access)

The Cross Section, Volume 9, Number 2, July 1962

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: July 1962
Creator: High Plains Underground Water Conservation District No. 1 (Tex.)
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
The Crystal Structure of Bis(m-Bromobenzoyl)Methane (open access)

The Crystal Structure of Bis(m-Bromobenzoyl)Methane

None
Date: July 10, 1962
Creator: Williams, D. E.; Dumke, W. L. & Rundle, R. E.
Object Type: Article
System: The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 3, March 15, 1962-June 14, 1962 (open access)

Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 3, March 15, 1962-June 14, 1962

An investigation was made to determine the extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Evaluation of susceptibility to time-dependent fracture was performed on an experimental Zr-- Al-- Sn-- Mo alloy containing 500 ppm hydrogen and the Canadian Zr-2.5Nb cladding material, as well as unalloyed zirconium and Zircaloy-2. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no time-dependent fracture was observed which could be attributed to the delayed failure phenomenon; an increased grain size or 20% prior reduction by cold rolling did not significantly affect this behavior. The curve of applied stress versus time to failure for the high-strength Zr--Al-Sn-- Mo alloy containing 500 ppm hydrogen indicated susceptibility to time-dependent fracture due to hydrogen absorption. Short-time data for Zr-<2.5Nb>2 in the heat-treated condition and containing 500 ppm hydrogen indicated that this material is insensitive to delayed failure. (auth)
Date: July 1, 1962
Creator: Weinstein, D. & Holtz, F. C.
Object Type: Report
System: The UNT Digital Library
Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor (open access)

Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Design criteria are presented for liquid-metal loop facilities for the Advanced Test Reactor. It was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. (M.C.G.)
Date: July 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor (open access)

Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Criteria are presented for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the ATR. This facility, a NaK-cooled in- reactor packaged loop based on the Pratt & Whitney Aircraft PW-19 loop design, is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions. (D.L.C.)
Date: July 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor (open access)

Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.
Date: July 1962
Creator: Babcock & Wilcox Company. Atomic Energy Division.
Object Type: Report
System: The UNT Digital Library
Detailed Stress Analysis of PM-2A Steam Generator for Tube Sheet (open access)

Detailed Stress Analysis of PM-2A Steam Generator for Tube Sheet

A detailed analysis of the PM-2A steam generator tube sheet revealed that is is safe from strain cycling damage. The pressure stresses, however, indicated that permanent deformation would take place in the tube sheet at hydrostatic test pressure of 1.5 times design pressure. (auth)
Date: July 20, 1962
Creator: Busuttil, J. J.
Object Type: Report
System: The UNT Digital Library
Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet (open access)

Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet

The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)
Date: July 11, 1962
Creator: Busuttil, J. J. & Chittum, R. A.
Object Type: Report
System: The UNT Digital Library
The Determination of Molecular Structure From Rotational Spectra (open access)

The Determination of Molecular Structure From Rotational Spectra

An analysis is presented concerning the average molecular configuration variations and their effects on molecular structure determointions. It is noted that the isotopic dependence of the zero-point is often primarily governed by the isotopic variation of the average molecular configuration. (J.R.D.)
Date: July 1, 1962
Creator: Laurie, V. W. & Herschbach, D. R.
Object Type: Report
System: The UNT Digital Library
Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina (open access)

Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina

A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized bed calciner. A quantitative correlation of the effect of these variables is presented. Alumina with an intra-particle porosity as low as five per cent can be generated by employing a suitable combination of low bed temperature and dilute aluminum feed concentration. Feed sodium concentration and product alpha alumina content were found to have minor effect on intra-particle porosity. Results also show that an inverse relationship exists between the nitrate content of the calcine and the calcination temperature. (auth)
Date: July 25, 1962
Creator: Wheeler, B. R.; Grimmett, E. S. & Buckham, J. A.
Object Type: Report
System: The UNT Digital Library
Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. First Quarterly Progress Report, April 1-June 30, 1962 (open access)

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. First Quarterly Progress Report, April 1-June 30, 1962

Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. The feasibility of U/ sup 235/ coated solid state detectors for use in these measurements is being studied. A theoretlcal investigation is also in progress on the effects of a multi-region assembly on the fundamental decay constant of injected bursts of neutrons. Other work is reported on the time-dependent neutron thermalization for bare multiplying media, particular attention is directed to the exponential time decay for pulsed bare multiplying homogeneous assemblies. Numerical expressions are given for the fundsmental eigenfunction and eigenvalue to the first and second order, respectively. An explicit analytical expression for the eigenfunction is included. (J.R.D.)
Date: July 1, 1962
Creator: Meyer, Paul & Garelis, Edwin
Object Type: Report
System: The UNT Digital Library