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A Study of Location Times for Positions Arranged on a Panel in a Random and an Ordered Manner
The results of an experimental pilot study on the location time, for a sequence of N specified positions on a panel, are given for 1 <_ N <_ 30. The positions to be located were randomly arranged on one set of panels and arranged according to an ordering scheme on a second set of panels. Th location time for N positions randomly arranged on a panel varies approximately as N(2). In the case of an order arrangement the location time is essentially proportional to N. Even for as few as 30 positions, the location time for an random arrangement was twelve times greater than for an order panel. For 60 positions the ratio would be 19, and for 90 positions the ratio would be 26.
Date:
May 25, 1955
Creator:
Beeler, J. R.
System:
The UNT Digital Library
Vapor Traps for Handling Liquid Sodium
An active program is a present underway to develop equipment to handle liquid metals. Among the metals being studied are sodium and sodium--potassium alloy (the latter commonly referred to as NaK). In many of the systems being studied this liquid metal is pressurized by inert gas in the lines. At times it is necessary to bleed off some of this gas from the system. Although the gas is allowed to escape at a temperature at which the vapor pressure of sodium is extremely small, it has been found that excessive amounts of sodium are present in this gas stream. Either this sodium collects in the lead-off pipes from the system as a solid, threatening to block the passage in which it is found, or it passes out into the atmosphere. In order to explain the presence of such a dangerous concentration of sodium in the exit gas stream, it has been proposed that the sodium vapor present in the the system at high temperatures condenses into a mist or aerosol on cooling. This aerosol is stable and will not readily de-entrain or condense onto the surfaces over which it passes. Another possibility is that the oxygen present with the inert …
Date:
August 25, 1951
Creator:
Erickson, A. J.; Gregory, C. L. & Lang, P. M.
System:
The UNT Digital Library
Studies on the Experimental Pathology and Biochemistry of the Pulmonary Granulomatosis of Beryllium Workers. Section II, Consolidated Progress Report. Supplement: a Review of the Physical Chemistry of Beryllium
The status of research is reviewed in a study of pulmonary granulomatosis in beryllium workers. Equipment for use in dust exposure studies is described. Preliminary results are reported from studies on the tissue distribution and pathological effects of beryllium dust in rats; the physical chemistry of solutions of beryllium salts; the effects of beryllium on enzyme systems, and the effects of ascorbic acid on beryllium excretion.
Date:
April 25, 1955
Creator:
Schepers, G. W. H. (Gerrit Willem Hendrik), 1914-
System:
The UNT Digital Library
The Helium Purification System for the Proposed Pebble Bed Reactor Experiment
A helium coolant side-stream purification system consisting of parallel sections for radioactive and non-radioactive de-contamination was designed for the proposed Pebble Bed Reactor Experiment. Primary equipment components are two gas coolers, gas heater, charcoal delay trap, CuO oxidizer, Molecular Sieve adsorber, and full flow filter. The charcoal delay trap is sized to provide a hold-up of 30 minutes for Kr isotopes, 6hr hold-up for Xe isotopes, and 99.9% retention of iodine isotopes resulting in "de-contamination factors" varying from l for Kr85 to 556 for I131. Non-radioactive de-contamination will result in a steady state concentration of CO2 in the coolant of 20.8ppm or less.
Date:
October 25, 1960
Creator:
Scott, C. D.; Finney, B. C. & Suddath, J. C.
System:
The UNT Digital Library
Estimate of Potential Fuel Reprocessing Revision #28 - Part A
The power and estimated reprocessing load are tabulated for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date:
June 25, 1959
Creator:
Ullmann, J. W.
System:
The UNT Digital Library
Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields
The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equation in order to locate the limiting features of the system. These features are then investigated by more powerful methods, which in turn provide guidance for development research in the laboratory.
Date:
May 25, 1959
Creator:
Alexander, L. G.
System:
The UNT Digital Library
Design Criteria for a Pile Oscillator
In the use of a reactor as a device to measure neutron cross sections, the pile oscillator is often employed because of its much higher sensitivity compared to that available in static reactivity measurements. The factor limiting the available in static reactivity measurements. The factor limiting the available sensitivity is the generation of random noise, which originates in the statistical nature of the chain reaction. In other words, the nuclear reactions which maintain the chain reaction do not proceed uniformly, but rather at rates which fluctuate in time around some average values. These fluctuations limit the accuracy of measurements in the reactor.
Date:
May 25, 1959
Creator:
Dresner, Lawrence
System:
The UNT Digital Library
Unit Operations Section Monthly Progress Report May 1959
The measured diffusivity of uranyl nitrate in water at 25ºC was 0.7*10^e cm^2/sec with about 40% average deviation. A program was started to develop nonnuclear uses for depleted uranium. Two continuous DRUHM reaction tuns were terminate due to erratic operation of the sodium metering system. In the second Fluorox run with crude UF, which lasted for 29 hr, a total material balance of 94.8% was obtained and 17.9& of the theoretical amount of UF was collected in cold traps and chemical traps.
Date:
August 25, 1959
Creator:
Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
System:
The UNT Digital Library
Compatibility Tests of Various Materials in Molten Sodium
Several compatibility test of various materials in contact in sodium under 500 psi pressure were conducted for 716 hr at 1500 F. Of the diffusion couples studies, the Inconel-beryllium system showed the largest amount al alloying. The reaction between molybdenum and beryllium resulted in the formation of two compounds, both of which were severely cracked in several areas. The molybdenum-INOR #8, and the INOR #8p type 316 stainless steel interfaces showed little if any alloying.
Date:
March 25, 1957
Creator:
Carlander, R. & Hoffman, E. E.
System:
The UNT Digital Library
Status Report on the Disposal of Radioactive Wastes
The new and as yet unsolved problems introduced by the production of large quantities of fission products and radioactive isotopes from fission or neutron capture present mankind a most complex technical, economic, and political problem. On one hand, the possibility of using the fission process to produce energy from an unexploited and abundant natural source is emerging from large programs of research and development. We are also beginning to see the promise of use of particulate and electromagnetic radiation for the good of man. On the other hand, we are presented with the problem of controlling the dangerous products of fission for periods of time measured in terms of many hundreds of years, periods longer than the effective tenure of any political state in history. We must not only devise ways of protecting ourselves in the present and for our lifetime but, in addition, we must establish the basic technical, social, and administrative control of vast quantities of artificial radioactivity that must remain effective for at least ten to twenty lifetimes.
Date:
June 25, 1957
Creator:
Culler, Floyd L., Jr. & McLain, Stuart
System:
The UNT Digital Library
Annual Report of the Boy Scouts of America: 1958
Annual report submitted by the Boy Scouts of America to Congress describing highlights from , activities, organizational leadership, and other information about scouting programs.
Date:
March 25, 1959
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1953
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1953, activities, programming, resources, organizational leadership, and other information about scouting programs.
Date:
March 25, 1954
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1942
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1942, activities, service reports, honors, finance, organizational leadership, and other information about scouting programs.
Date:
March 25, 1943
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Annual Report of the Boy Scouts of America: 1937
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1937, activities, service reports, finance, honors, organizational leadership, and other information about scouting programs.
Date:
March 25, 1938
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.
Date:
October 25, 1962
Creator:
Howard, C. L.
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961
This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
Date:
August 25, 1961
Creator:
Danielson, D. W.
System:
The UNT Digital Library
Swaging Over Unground Pellets
This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date:
January 25, 1961
Creator:
Brown, R. L.
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.
System:
The UNT Digital Library
Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System
This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date:
July 25, 1959
Creator:
Craig, W. D.
System:
The UNT Digital Library
Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station
This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.
Date:
August 25, 1958
Creator:
Commonwealth Edison Company
System:
The UNT Digital Library
The Determination of Fission Product Gamma Doses
In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.
Date:
February 25, 1957
Creator:
Ruehle, William G.
System:
The UNT Digital Library
The Chemistry of Vanadium: A Summary of the Non-Project Literature Through November, 1952
The non-project literature concerning the chemistry of vanadium has been summarized through November, 1952. The report is presented in terms of izo- and heteropoly vanadates and cationic forms of pentavalent vanadium, complexes of di-, tri-, and pentavalent vanadium, and oxidation potentials of various vanadium systems. A bibliography of 93 references is included.
Date:
June 25, 1954
Creator:
Frank, Andrew J.
System:
The UNT Digital Library
A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid
Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be 6¢ per pound of HF.
Date:
May 25, 1956
Creator:
Marinsky, J. A. & Giuffrida, A. J.
System:
The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I.
This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date:
November 25, 1955
Creator:
Williams, D. V. P.
System:
The UNT Digital Library