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Metallurgical Examination of HRT Leak Detector Tubing and Flanges
After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It appears that chloride contamination entered the system in a portion of the first lot of tubing used for the shield penetration. The exact source of the chloride cannot be determined, but after considering the results and visiting the manufacturer's plant, it appears most likely the contamination was during the manufacturing process.
Date:
January 31, 1957
Creator:
Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Object Type:
Report
System:
The UNT Digital Library
Thorex Pilot Plant ; System for Concentrating Second Uranium Cycle Product
A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of the total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29 g/liter; the average concentration in the evaporated solution was 298 g U/liter and in the product solution was 199 g/liter. Radiation readings of bottles containing product solutions were taken with a hard-shell cutie pie immediately after each run, and these readings ranged from 35 to 1100 mr/hr. The radiation levels of the bottles of product solution shipped averaged 78 mr/hr. Bottles of product solution reading in excess of 300 mr/hr, maximum allowable for shipment. were reprocessed in the second-cycle solvent extraction system (Thorex) and reconcentrated. The products from seven runs had radiation levels in excess of 300 mr/hr at the time of concentration, or the activities had grown to that level by the time of shipment. The …
Date:
January 28, 1957
Creator:
Albrecht, W. L.
Object Type:
Report
System:
The UNT Digital Library
Polarographic Analysis of UNH in the IAW Stream
The following report describes two rapid, micro methods for the determination of UNH in Redox waste samples that had been developed fir the concentration range 0.2 to 100 g/l.
Date:
January 17, 1949
Creator:
Alkire, G. J. & Carson, W. N.
Object Type:
Report
System:
The UNT Digital Library
Completion Report An Automatic Fuel Element Stamping Machine
This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date:
January 12, 1960
Creator:
Allen, C. H.
Object Type:
Report
System:
The UNT Digital Library
The Injection Casting of Plutonium
Plutonium metal can be injected into cold metal molds to form castings with thin walls. The operation is performed in a vacuum chamber, using an inert gas as the injecting medium. Sound pieces free of gas cavities can be made using either pure or delta-stabilized plutonium. This report describes the equipment and techniques used to cast a typical thin section piece in the form of a 6 in. diameter, 45' cone.
Date:
January 1959
Creator:
Anderson, J. W.
Object Type:
Report
System:
The UNT Digital Library
The Homopolar Device
This paper is intended as a preliminary report on the Homopolar configuration (axial magnetic field with radial electric field), which is the rotating configuration most thoroughly studied thus far. The analysis presented in this paper applies principally to the "ideal" Homopolar, that is, the configuration free from electrode-sheath drops and other disturbing but remediable phenomena. Design considerations for various interesting plasma appliances are derived and documented with preliminary experimental results. The experiments have been carried out under high-density (pinch-type) conditions which favor the creation of a totally rotating plasma and the actual physical measurement of the characteristics of such a plasma. When larger models of the Homopolar are built, it will be possible to use the present pinch-type technique of plasma formation at much lower density, just as has been done in the case of the toroidal stabilized pinch.
Date:
January 1958
Creator:
Anderson, O. A.; Baker, W. R.; Bratenahl, A.; Furth, H. P.; Ise, J., Jr.; Kunkel, Wulf B. et al.
Object Type:
Report
System:
The UNT Digital Library
Some Considerations on the Configuration and Stability of the H2 Temperature Control Loops of the 80" Bubble Chamber
There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression for some physical quantities such as film heat transfer coefficients entering as major parameters the process equation.
Date:
January 7, 1964
Creator:
Androulakis, John G.
Object Type:
Report
System:
The UNT Digital Library
Aging of Al-Li Alloys - Part I
Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) or the (111) planes of the aluminum matrix were observed in overaged specimens."
Date:
January 1959
Creator:
Angerman, C. L.
Object Type:
Report
System:
The UNT Digital Library
Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element
The following report presents neutron-flux measurements made with a concentric-cylinder element (Mark II) and includes axial, radial, and peripheral flux distributions.
Date:
January 29, 1959
Creator:
Anno, James N.; Fairand, Barry P. & Chastain, Joel W., Jr.
Object Type:
Report
System:
The UNT Digital Library
Biological Effects of Thermal Neutrons and the B10 (n,c) Li7 Reaction
Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a range in tissue of about 8-14μ or approximately 1 cell diameter (1). This fact and the reported favorable partition of boron between tumor and the normal brain suggested a possible therapeutic usefulness which has been investigated clinically. The object of our study is to document the biological effects of the B10 (n,α) Li7 reaction on the brain of dogs injected with boron-10 30 minutes prior to irradiation with thermal neutrons. For this, we felt it desirable to estimate a dose for the boron-10 reaction which if exceeded, produces destruction of normal tissue. This dose could then be a reference dose to be utilized as a maximal limit for the irradiation of normal tissue. We have assured that the largest fluence …
Date:
January 13, 1964
Creator:
Archambeau, J. O.; Alcober, V; Calvo, W. & Brenneis, H.
Object Type:
Report
System:
The UNT Digital Library
Dose-survival Curves for HeLa Cell Cultures Using Thermal Neutrons and the B10 (n,α)Li7 Reaction
The biological evaluation of the thermal neutron capture reaction of boron-10, B10 (n,α)Li7 + 2.786 MeV, has previously been studied, using different particles from the boron-10 thermal neutron capture reaction compared with 250 kvp x-rays has been reported as 1.05 for spleen-thymic weight reduction (1), as 1.5 to 2.0 for skin lesions in pigs (2), and 1.87 for skin lesions of the rabbit's ear (3). The significance of such a calculation is felt to be unreliable for the boron-10 reaction in animals because of the vagaries of dose determination resulting from irregular boron distribution, and by the presence of an adventitious irradiation from fast neutrons and capture gammas that is inadequately determined at present. Our present experiment attempts to circumvent the difficulties attendent to studies of the boron-10 reaction in animals by comparing the effect of this reaction on the proliferative capacity of HeLa cells with those produced with 250 kvp x-ray.
Date:
January 13, 1964
Creator:
Archambeau, J. O.; Drew, R. M. & Robertson, J. S.
Object Type:
Report
System:
The UNT Digital Library
Experiments on a Large Volume Electron-Cyclotron Heated Plasma
As part of the thermonuclear effort at Oak Ridge National Laboratory, large volume high-beta plasmas have recently been produced by microwave power at the electron-cyclotron frequency. The original work was done with 13-cm microwave radiation in a magnetic mirror and was reported at Salzburg. Since that time, higher frequency and higher power radiation has been used in a succession of experiments. The current experiments involve heating a plasma in the EPA Facility which has a 3:1 magnetic mirror ratio. Up to 50-kw CW of 3-cm microwave power are applied to the plasma in a large volume cavity.
Date:
January 1963
Creator:
Ard, W. B.; Becker, M. C.; Dandl, R. A.; Eason, H. O.; England, A. C. (Alan Coulter), 1932- & Haas, G. M.
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: January 1957
A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Initial contacts were made at National Reactor Testing Station and Hanford Works, design conditions for the proposed reactor vessels were reviewed, estimates of heating rates caused by radiation and the pluggage of fuel passages were computed, and design parameters for the LMFRE were established.
Date:
January 1957
Creator:
Babcock & Wilcox Company
Object Type:
Report
System:
The UNT Digital Library
Cool-Down Refrigeration Requirements for 80" Bubble Chambers
The purpose of this report is to determine the amount of refrigeration capacity required to cool down the 80" bubble chamber from ambient temperature to liquid hydrogen temperature.
Date:
January 7, 1964
Creator:
Bamberger, J. A.
Object Type:
Report
System:
The UNT Digital Library
General Description of the 80" Bubble Chamber Refrigeration System
Reliability of individual components and the ability to produce refrigeration even if one or two of these components should be in operable are the prime design parameters of this cycle. Each component was looked at with these two parameters in mind and any item that had obvious objections was either rejected or backed up with another piece of equipment. Along this line, you will notice (refer to line schematic) two hydrogen compressors and two nitrogen compressors; for full capacity all are required. However, in the event of the loss of use of one of these compressors, it will still be possible to produce at least 50% of the rated capacity. To eliminate outside influences, the cycle was designed around what may be called a closed cycle cascade system; with the assumption that there is no loss of power, cooling water, the equipment can run indefinitely. The nitrogen and hydrogen cycles are of the Simple Linde type with pre-cooling making use of the Joule-Thompson Effect for the refrigeration produced. The low-temperature components of the cycle have no moving parts other than valves, consisting entirely of counter-flow heat exchangers to lower the temperature of the incoming high-pressure gas to a level where …
Date:
January 7, 1964
Creator:
Bamberger, J. A.; Brown, D. P. & Jensen, J. E.
Object Type:
Report
System:
The UNT Digital Library
Hydrogen Refrigerator Design Capacity for 80" Chamber
When the design of the refrigerator was begun, one of the important parameters was refrigeration capacity required. In order to estimate the required hydrogen refrigeration load the following had to be considered: 1. Dynamic Load due to pulsing of the chamber. Although this has been determined some two years ago through test work, it has not been published as of this date and will be presented here. 2. Static losses due to conduction, radiation, and convection. This is covered by Eng. Note BC-03-0-B. 3. Cool-down requirements. This is covered by Eng. Note BC-03-0-C.
Date:
January 7, 1964
Creator:
Bamberger, J. A.; Brown, D. P. & Jensen, J. E.
Object Type:
Report
System:
The UNT Digital Library
Interim Report of the Fuel Processing Group
"This report covers mainly the work completed since the last interim report, HNL Log No. 0-4714. This report includes results from studies of the rare earth distribution in bismuth-uranium and fused chloride and studies of fused chloride behavior."
Date:
January 15, 1952
Creator:
Bareis, D. W.
Object Type:
Report
System:
The UNT Digital Library
Spinning of Columbium & Columbium 1%- Zirconium Tubing
The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests performed for objective No. 1.
Date:
January 19, 1961
Creator:
Barker, Wharton R.
Object Type:
Report
System:
The UNT Digital Library
Time Dependence of Space Charge Beam Losses in the Cosmotron
An investigation was made of Cosmotron intensity versus time through the entire time interval from the beginning of injection to the completion of r-f capture. The induction electrode signal was used for the instantaneous measurement of beam intensity. Oscilloscope displays of the signal were photographed and traced. Base lines were filled in on the tracings and the area of the pulses measured with a polar planimeter. It was found that the relation losses of beam intensity increase with injection intensity (total injected charge), and that most of the losses take place in the time interval between the end of injection and the completion of the first synchrotron oscillation
Date:
January 4, 1962
Creator:
Barton, M. Q. & Sacharidis, E. J.
Object Type:
Report
System:
The UNT Digital Library
Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method
The feasibility of determining particle sizes in the submicron range by employing an activation analysis - centrifugation method has been demonstrated. It is believed that this method is now applicable to the analysis of thorium oxide for submicron particles. The same techniques are, in most instance, usable in determining particle sized in other sample materials.
Date:
January 29, 1957
Creator:
Bate, L. C. & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959
The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date:
January 15, 1960
Creator:
Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Object Type:
Report
System:
The UNT Digital Library
Electroplates on Thorium
Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."
Date:
January 9, 1953
Creator:
Beach, John G.; Schickner, W. C.; Vaaler, L. E. & Faust, Charles L.
Object Type:
Report
System:
The UNT Digital Library
Homogeneous Reactor Test Summary Report for the Advisory Committee on Reactor Safeguards
The Homogeneous Reactor Test (HRT) is the experimental reactor facility (Frontispiece) being designed and constructed at ORNL as the next step in homogeneous reactor development between the 1-Mv HRE and a "full-scale" power station. The HRT will provide an integrated test at 5 to 10 Mv for the flowsheet and equipment designs on which the full-scale effort will be based. Furthermore, its design is such that several homogeneous systems which require essentially the same operating equipment may be tested with comparatively minor modifications of the original reactor installation. The reactor will be assembled in the building which housed the HRE, located in the experimental reactor exclusion area approximately one mile south of the oak ridge laboratory. (See figure 1) / It is the purpose of this report to provide information with which the hazardous aspects of this reactor may be evaluated. Briefly, it will be shown after a statement of purpose and a general description of the reactor that: 1. The design characteristics and equipment requirements are such that escape of highly reactive material from the reactor piping is unlikely. 2. Should the entire core and blanket contents suddenly escape from the reactor system, a seal-welded steel tank surrounding the …
Date:
January 5, 1955
Creator:
Beall, S. E. & Visner, S.
Object Type:
Report
System:
The UNT Digital Library
MTR Test Equipment
From abstract: "Sample holders and monitoring equipment were designed and fabricated for use in the irradiation of experimental shapes of fuel and target materials in the beryllium reflector of the Materials Testing Reactor. The samples were held in aluminum cases designed to replace certain beryllium blocks of the reflector. Sample holders of alternate designs were made to permit irradiation of samples in the reflector at locations where the shape or position of the reflector blocks would not permit the use of the original design."
Date:
January 1956
Creator:
Bell, W. F.
Object Type:
Report
System:
The UNT Digital Library