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NACA Research Memorandums
342
NACA Technical Notes
248
Atomic Energy Commission Reports
127
United States Geological Survey Reports
86
Trace elements investigations report
53
Hanford Works Reports
49
University of California Radiation Laboratory Reports
48
HW (Series)
35
Battelle Memorial Institute Reports
23
NACA Technical Reports
23
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An Estimation of the Explosion Hazard During Reprocessing of Metallic Uranium Fuel Elements Metallurgically Bonded to Zircaloy Cladding
Through the years, considerable effort has been expended in studies of the explosive reactions sometimes observed in the dissolution of uranium-zirconium alloys in nitric acid. It has been shown (1) that such reactions result from the rapid oxidation of finely dived solids released by the preferential dissolution of the metallic matrix. The explosive portion of such solids has been identifies (1) as an intermetallic compound with the approximate composition UZr2. This compound, referred to as the epsilon phase in previous work, has more recently (2) been termed the delta phase. The latter designation will be employed here.
Date:
September 30, 1959
Creator:
Sanson, J. L.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant
From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date:
September 30, 1959
Creator:
Linenberger, G. A.
Object Type:
Report
System:
The UNT Digital Library
All In-Well Permeability Testing Packer
Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
Date:
September 29, 1959
Creator:
Raymond, J. R.
Object Type:
Report
System:
The UNT Digital Library
Current Beryllium Literature : A Selected Bibliography, January 1958 - August 1959
"This bibliography lists selected articles on beryllium which have appeared in journals received in the library of the Lawrence Radiation Laboratory, Livermore, California and articles, reports, and books which have appeared in the following abstracting services between January, 1958 and August 1959."
Date:
September 29, 1959
Creator:
Lane, Zanier D.
Object Type:
Report
System:
The UNT Digital Library
N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)
This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date:
September 25, 1959
Creator:
Bailey, J. A. & Shields, C. M.
Object Type:
Report
System:
The UNT Digital Library
A Test of the Refraction Seismic Method on the Hanford Project
Information was desired on applicability of seismic methods of geophysical exploration in helping to better define and refine hydrological and geological factors affecting ground disposal of liquid radioactive wastes. To date most of information on the area geology has been obtained from surface mapping and well drilling, although it has long been recognized that geophysical techniques may greatly assist in defining the geology of the region. Although direct measurements are generally preferred to indirect measurements have proven extremely valuable in many applications. Careful analysis of field data from geophysical measurements, and correlation with known geologic conditions, should provide significant knowledge of earth formations. Geophysical methods do not directly determine depth, type and composition of underground earth materials, but rely rather on detecting differences in physical properties (elastic wave velocity, magnetic susceptibility, density or electrical resistivity) of such earth materials.
Date:
September 25, 1959
Creator:
Raymond, J. R.
Object Type:
Report
System:
The UNT Digital Library
Results of a Force Test of Four Configurations of the Hi-Lo Instrumented and Chaff Rockets in the Sandia Corporation 12 x 12 inch Transonic Wind Tunnel (Program III-46)
Abstract: Force, moment, and center of pressure information are presented for four models of the Hi-Lo configuration.
Date:
September 24, 1959
Creator:
Arnold, J. W.
Object Type:
Report
System:
The UNT Digital Library
Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion
Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal facilities into ground water on the basis of short, laboratory soil columns and equilibrium experiments (6,7). In this method it is assumed that the shape and position of the breakthrough curve is the same under laboratory conditions as in the larger scale field case. It is also assumed that the "column volume" or amount of soil effectively used for fission product sorption is that directly under a disposal facility without considering any spreading of waste solutions. These assumptions are known to be on the conservative side, but the degree of conservativeness is not known.
Date:
September 22, 1959
Creator:
Nelson, J. L.
Object Type:
Report
System:
The UNT Digital Library
Temperatures and Thermal Stresses in Hexagonal Tubes and Pierced Plates With Internal Heat Sources
From abstract: "Steady temperatures and thermal stresses are determined for long hexagonal tubes having round holes for the case of uniform internal heat generation and a fluid-cooled inside surface. Thermal stresses are also determined for thick plates pierced by holes on an equilateral triangular pattern and for hexagonal tubes having a hexagonal hole with rounded inside corners. Stresses in the end regions of tubes are also investigated."
Date:
September 22, 1959
Creator:
Meuser, Robert B.
Object Type:
Report
System:
The UNT Digital Library
Pressure and Thermal Stresses at a Pipe Attachment to a Sphere
Abstract: Design nomographs and equations have been prepared for determining the bending stresses and hoop stresses at the junction of a cylinder and sphere when: (1) Internal pressure exists in the sphere and (2) There is a difference in average temperature between the cylinder and the sphere. A correlation of calculated stresses and photoelastically determined stresses for models with internal pressure is presented.
Date:
September 21, 1959
Creator:
Deagle, Lorenzo
Object Type:
Report
System:
The UNT Digital Library
Filtering Abrasive-Wheel Uranium Cuttings
Extremely radioactive particles result from the abrasive wheel cutting of irradiated fuel elements in the cut-off cell located in the 327 Building. Due to the use of water during the cutting operation these particles are in suspension and must be removed before the liquid can be discharged to the liquid waste tanks in the 340 building. The filters presently employed in the cell total activity discharged to the 340 Building tanks is attributed to the particles which pass these filters. With the start-up of a new, larger cut-off cell the cutting is expected to increase considerably, thereby increasing the amount of radioactive cuttings requiring disposal. The installation of equipment which would more efficiently remove the suspended particles would (1) reduce the activity level of wastes disposed to ground, (2) reduce the radiation exposure level to drivers who truck the wastes to the 200 Area, and (3) prevent the forming of localized high radiation zones due to the deposition of particles in the waste line in the 327 Building.
Date:
September 18, 1959
Creator:
Postma, A. K. & McCorrmack, J. D.
Object Type:
Report
System:
The UNT Digital Library
Minutes of Criticality Instrumentation Meeting Hanford Atomic Products Operation August 17 and 18, 1959
At the request of the Hanford Operations Office of the Atomic Energy Commission, a criticality instrumentation meeting was held at Hanford on August 17 and 18, 1959. The purposes of the meeting were: (a) to review types of criticality control and/or alarm instrumentation at each site, their problems, shortcomings and potential obsolescence; (b) to discuss instrumentation in the area if approaching criticality; and (c) to consider for material balance purposes, the feasibility of devising instruments to detect the buildup of plutonium and enriched uranium bearing residues in process systems.
Date:
September 16, 1959
Creator:
Brown, C. L.
Object Type:
Report
System:
The UNT Digital Library
Division of Reactor Development Programs Monthly Report- August 1959
Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density versus composition still indicate a drastic reduction in UO2 sinterability with even the slightest additions of PuO2 and a rapid increase with PuO2 contents greater than 20 weight percent. The following table compares densities of pure UO2 and PuO2 after an eight hour soak time:
Date:
September 15, 1959
Creator:
McEwen, L.H.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Countermeasure System Components and Operational Procedures
"The objective of project 32.3 was to evaluate some operational characteristics of a radiological shelter and to determine values for some countermeasures-system parameters."
Date:
September 15, 1959
Creator:
Strope, W. E.
Object Type:
Report
System:
The UNT Digital Library
Interpretation of Westwood, New Jersey Rainfall Data
"Progress is reported in an evaluation of fission product concentration in rain as a function of time, location, and meteorological setting. Data on rainfall collected at Westwood, N. J., were analyzed for information on the mechanisms of fallout deposition, seasonal variations in fallout, the stratospheric residence time of W/sup 185/ resulting from Operation Hardtack, and the accuracy of pot samplers for sample collection. Data from other collection stations were also analyzed for consistency with Westwood data."
Date:
September 15, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
OMR Control-Safety Rod Component Development Tests
Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date:
September 15, 1959
Creator:
Howell, J. D.
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of the Potential to Kinetic Energy Conversion Process in the Stratosphere
The potential to kinetic energy conversion process in the lower stratosphere is evaluated using adiabatically derived vertical velocities for the North American region for a five-day period. Preliminary results suggest the possibility that on the average the kinetic energy of stratospheric motions may not result from a conversion of potential energy within the stratosphere. The further implication is that stratospheric motions are mechanically driven by the motions in the adjacent layers of the atmosphere.
Date:
September 15, 1959
Creator:
White, Robert M., 1923-2015 & Nolan, George F.
Object Type:
Report
System:
The UNT Digital Library
Feasibility Study of Transient Version of Astron Thermonuclear Reactor : Part 1
The following report proposes a concept of a transient version of Astron thermonuclear reactor while describing the basic concepts of the reactor and the design criteria.
Date:
September 14, 1959
Creator:
Chang, C. C.
Object Type:
Report
System:
The UNT Digital Library
Energy Dissipation by Fast Electrons
Report discussing the energy dissipated by fast electrons at different distances from monoenergetic electron sources, for plane perpendicular and point isotropic sources including tabulations and a summary of the theoretical methods and data utilized, and a table of spatial moments.
Date:
September 10, 1959
Creator:
Spencer, L. V.
Object Type:
Report
System:
The UNT Digital Library
Fretting Corrosion Irradiation Tests
The Zircaloy-a clad, swaged UOa, 19-rod cluster fuel element for the PRTR was designed to use Zircaloy-a wire spirally wrapped around the fuel rods as spacing members. Such use of unbonded, Zircaloy-a spacers introduced the possibility of fretting corrosion. This paper reports preliminary irradiation tests conducted to determine whether or not such corrosions occurs in this fuel element design.
Date:
September 10, 1959
Creator:
Millhollen, M. K.
Object Type:
Report
System:
The UNT Digital Library
Quality Standards and Tests for Swaged Fuel Cladding
The basic process for fabricating a swaged fuel rod is simple, easy to control and inexpensive. A zircaloy tube is filled with uranium dioxide powder, the ends temporarily plugged and the loaded tube is swaged to compact the UO2 powder to the required density. The swaged rod is then cut to length and counterbored and then end cape are welded into each end. After several tests and inspections, nineteen rods which meet the quality standards are assembled into a single fuel element ready for irradiation.
Date:
September 10, 1959
Creator:
Olson, R. E.
Object Type:
Report
System:
The UNT Digital Library
Zirconium Tube Rupture from Localized Overheating
Very little information and data are available on the various physical properties of Zircaloy tubing, especially the high temperature- high pressure failure aspects. As greater use is being made of the low cross-sectional properties of this material in the design and development of reactor components, it was considered desirable to determine the type of failure that would be experienced under conditions of a localized over-heating. This hot-spot could be caused by "cocked" or warped fuel elements coming in direct contact with the process tube, thereby preventing adequate cooling media at the particular location.
Date:
September 9, 1959
Creator:
Jackson, P. M.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Section C Monthly Progress Report August 1959
Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date:
September 8, 1959
Creator:
Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Object Type:
Report
System:
The UNT Digital Library
Development of Ribbed Jacket Tubing for PTRT
One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel elements.
Date:
September 4, 1959
Creator:
Aungst, R. C.
Object Type:
Report
System:
The UNT Digital Library