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A Solution of the Distributional Error Problem in Cytophotometry
Use of that portion of the characteristic curve of photographic film in which transmission is linear with log exposure eliminates the distributional error and thus makes possible the assessment of total mass of an inhomogeneously distributed cell consistent without scanning or measuring the cell's projected area. Measurement consists of obtaining the difference in output of a photocell receiving the total light transmitted by a photomicrograph of the cell, and a photomicrograph of the microscope field illumination against which the cell was photographed. A method of making such measurements is given, and its basis is described.
Date:
December 19, 1961
Creator:
Adams, Lawrence R. & Sondhaus, Charles A.
Object Type:
Report
System:
The UNT Digital Library
Diffusion Equation Green's Functions for Box Problems
The use of diffusion theory to attempt to reproduce the chemical data of Hicks and Stevenson for the spatial distribution of neutrons in a solid block of uranium that is bombarded by 190 Mev neutrons is described.
Date:
December 27, 1951
Creator:
Adelman, F.; Lepore, J. & Rosenblum, M.
Object Type:
Report
System:
The UNT Digital Library
Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients
It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.
Date:
December 23, 1959
Creator:
Allen, C. W.
Object Type:
Report
System:
The UNT Digital Library
Kinetics of the Los Alamos Power Reactor Experiment (LAPRE)
A theoretical study of the kinetics of a model of the Los Alamos Power Reactor Experiment (LAPRE) was made through integration of the dynamic equations with the IBM 701 computer. The stability is investigated under various conditions of power demand, rod-induced reactivity changes, and other conditions especially applicable to LAPRE. The results are given in graphical form, along with conclusions as to appropriate conditions of operation.
Date:
December 1953
Creator:
Allred, John C. & Carter, David S., 1926-
Object Type:
Report
System:
The UNT Digital Library
Regeneration of Silver Reactors
A study of the variables involved in regeneration was undertaken to determine means of improving the regeneration efficiency and increasing the useful life of a reactor. Information gained from regeneration studies on a 4-inch-diameter by 8-foot-high column indicates that the present regeneration procedure is optimum as to quantity, concentration, and rate of addition of regenerant solution. It appears feasible to restore a plugged reactor by washing off all the silver nitrate from the packing and recoating by a normal regeneration cycle. Such a procedure could be utilized only if there is sufficient dead space in the bottom of the reactor to hold the wash solution.
Date:
December 27, 1955
Creator:
Amos, L. C.
Object Type:
Report
System:
The UNT Digital Library
LRL-Nevada Drill Hole Survey Technique
The demands of the scientific programs of the Lawrence Radiation Laboratory at the Nevada Test Site have necessitated the development of special drill hole survey techniques. These techniques, in general, have made possible the attainment of greater survey accuracies than are ordinarily obtained by the drilling industry in the course of normal survey work. For drill holes requiring a moderately high degree of location accuracy, standard survey equipment, manufactured by Eastman Oil Well Survey Company was adapted by LRL to meet this need. Where an extremely high degree of survey accuracy and control of drilling effort is necessary, such as in the drilling and survey of line-of-sight holes, special optical equipment was developed. The modifications of equipment, refinements in procedures, and special techniques necessary to adapt this equipment to meet the more demanding accuracy requirements of scientific programs are discussed. The overall techniques of survey, equipment used, and the accuracies obtained together with results of completed surveys showing a comparison with standard land survey methods are also discussed and illustrated in some detail.
Date:
December 1960
Creator:
Anderson, Arthur L.; Skousen, Lester P. & Bennett, Walter P.
Object Type:
Report
System:
The UNT Digital Library
Comments on Equipment for a PRTR Water Quality Control Laboratory
This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
Date:
December 1, 1959
Creator:
Anderson, H. J. & Peray, R. E.
Object Type:
Report
System:
The UNT Digital Library
Steady State Temperature Distributions in Hollow Slugs
This document is a sequel to HW-30226, "Steady State Temperature Distribution in a Solid Slug." A primary feature of the present as well as the former paper is a treatment of the stand heat flow equation in a manner which accounts accurately for the dependence of the thermal conductivity, K, on temperature, v.
Date:
December 31, 1953
Creator:
Anselone, P. M.; Banks, D. O. & Dean, R. Y.
Object Type:
Report
System:
The UNT Digital Library
Heat Flow Problems with Temperature Dependent Thermal Conductivity
Various non-linear calculations for heat conduction in an istropic, homogeneous medium are presented.
Date:
December 10, 1953
Creator:
Anselone, Philip M.; Banks, D. O. & Dean, R. Y.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program
The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
Date:
December 5, 1962
Creator:
Antony, K. C. & Jones, L. T.
Object Type:
Report
System:
The UNT Digital Library
Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952
Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date:
December 15, 1952
Creator:
Argonne National Laboratory. Reactor Engineering Division.
Object Type:
Report
System:
The UNT Digital Library
Reactor Engineering Division Quarterly Report September 1, 1953 through November 30, 1953
Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date:
December 15, 1953
Creator:
Argonne National Laboratory. Reactor Engineering Division.
Object Type:
Report
System:
The UNT Digital Library
Relative Biological Hazards of Radiations Expected in Homogeneous Reactors TBR and HPR
An evaluation of the relative health hazards of radioisotopes produced in nuclear reactors is reported. The most important hazards were indicated to be I131, the Sr90 - Y90 chain, the Ce144 -Pr144 chain, Sr 89, the Ba140-La40 chain, Y91, the Zr95-Nb95 chain, Pr143, La140 , and Pa233. The most critical body organs affected by air-borne contamination are the thyroid gland, the bone marrow, the lungs, and the gastrointestinal tract. Where possible, continuous daily removal of gaseous and solid fission products from the reactor environment can be shown to permit very significant reductions in the total hazards. Homogeneous reactors, such as the Thermal Breeder Reactor and the Homogeneous Plutonium Producer Reactor, specifically studied in this report, are designed with daily removal cycles and may be considered potentially safer than heterogeneous reactors.
Date:
December 2, 1955
Creator:
Arnold, E. D. & Gresky, A. T.
Object Type:
Report
System:
The UNT Digital Library
Factors Affecting Properties of Extruded Compacts of Crystal Bar Zirconium
The following report analyzes various experiments made to discover factors that may affect properties of extruded compacts of crystal bar zirconium.
Date:
December 5, 1955
Creator:
Arnold, Samuel V.
Object Type:
Report
System:
The UNT Digital Library
Solutions of the Reactor Kinetics Equations for Time-Dependent Reactivities
Abstract: The reactor kinetics equations are combined into a single integral equation whose kernel describes the time-dependent characteristics of the reactor including six delayed groups of neutrons. Numerical solutions of the integral equation are given for constant, linear, and ∫sin²kx dx reactivities. An approximate solution of the integral equation is obtained which provides a basis for the formulation and solution of the reactor system control problem using the methods of servomechanisms theory. The reactor frequency response function, a product of the approximate solution, is calculated and plot given.
Date:
December 14, 1955
Creator:
Ash, Milton S.
Object Type:
Report
System:
The UNT Digital Library
Poisoning and Production in a Power Plant
The yield of 49, the efficiency of production of 49, and poisoning in a power plant are discussed. Only the crudest of estimates of the poisoning are possible: these indicated that production will probably not be hampered by poisoning. In this case the yield of 49 could be as high as 3 kg/ton but only about 2 kg/ton is compatible with a fairly high efficiency. In the case that production is stopped by poisoning, smaller yields, proportional to the tolerable loss in k, are obtained. In this case the yield will be improved by a factor of 2 or 3 if only the most poisoned parts are extracted and replaced by new uranium.
Date:
December 15, 1942
Creator:
Ashkin, J.; Christy, Robert F., 1916-2012 & Feld, Bernard T. (Bernard Taub), 1919-1993
Object Type:
Report
System:
The UNT Digital Library
Scintillation Counting of Natural Uranium Foils
Report discussing studies of uranium scintillation counting, which discriminates against certain types of decay and fission activity.
Date:
December 1952
Creator:
Axtmann, Robert C. & Stutheit, James S.
Object Type:
Report
System:
The UNT Digital Library
Initial Operation of the Standard Pile
From abstract: "The Standard Pile was first brought to criticality on July 25, 1953. The first two months of operation permitted calibration of the reactor and preparation of it for use as a neutron source in exponential experiments."
Date:
December 1953
Creator:
Axtmann, Robert C.; Heinrich, L. A.; Robinson, R. C.; Towler, O. A. & Wade, J. W.
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: December 1956
A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Preliminary design studies for nuclear reactor development and its components were reported.
Date:
December 1956
Creator:
Babcock & Wilcox Company
Object Type:
Report
System:
The UNT Digital Library
Closed Extensions of the Laplace Operator Determined by a General Class of Boundary Conditions
This paper is concerned with the spectral theory of closed operators in Hilbert space determined by the Laplace operator and certain general boundary conditions. Using the method of J.W. Calkin, we treat the case of a bounded domain in E(m) with C(1,1) boundary, and, in addition, extend the method to cover the case for which the operator L in the boundary condition is not necessarily self-adjoint. It is shown that there exists an appropriate linear close of functions [formula] such that the operator in the Hilbert space [formula] and [formula] is self-adjoint. In potential theoretic terms it is the set of all sums p + h, where p is the potential due to a charge g in G and h is the potential due to a surface charge f on ∂G and h is a potential due to a surface charge f on G, where g and f are, respectively, square integrable over G and ∂G
Date:
December 1960
Creator:
Badè, W. G. (William G.), 1924-2012 & Freeman, R. S.
Object Type:
Report
System:
The UNT Digital Library
A Safety Rod Actuator
From abstract: "A windlass that operates a safety rod for a nuclear reactor was developed to decelerate the rod after it drops under emergency conditions into the reactor. The windlass is designed to convert the kinetic energy of the falling rod as it nears its limit of travel to rotational energy in the windlass. The conversion is accomplished without the aid of an external power source or an auxiliary snubbing mechanism."
Date:
December 1954
Creator:
Baker, D.; Llewellyn, W. E. & Maloney, J. P.
Object Type:
Report
System:
The UNT Digital Library
Thermal-Neutron Flux at the HRE-2 Core Wall, Determined from Zircaloy-2 Induced-Activity Measurements During Runs 13, 14, 16, 17, 18, 19, 20 and 21.
The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-in. from the core center.
Date:
December 20, 1960
Creator:
Baker, J. E.
Object Type:
Report
System:
The UNT Digital Library
Computations for AGS Experimental Beams: Description of Computer Program
Description of a computer program which optimizes the locations and strengths of magnets for experimental beams at the Brookhaven AGS written for the IBM 7090 computer. Layout, method, and routines are given particular attention, and representative data cards are shown.
Date:
December 15, 1961
Creator:
Baker, Winslow F.
Object Type:
Report
System:
The UNT Digital Library
Neutron Economy of Various Converter Reactor Designs
The following report determines how many neutrons are being absorbed in various converter reactor designs, how many neutrons leak from the reactor and the breakdown between fast and thermal leakage. Another interest this paper examines is to determine how many neutrons are absorbed in thorium in the resonance region, at thermal energy, and in the blanket.
Date:
December 12, 1951
Creator:
Balent, Ralph
Object Type:
Report
System:
The UNT Digital Library