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Ion Energy Distribution, Energy Degradation, and Exponentiation Criteria in a Plasma Formed by Beam Trapping and Charge Transfer (open access)

Ion Energy Distribution, Energy Degradation, and Exponentiation Criteria in a Plasma Formed by Beam Trapping and Charge Transfer

An approximation is derived for the time constant which characterizes the rate of energy loss of fast ions moving through a plasma. Using particle and energy-balance equations a simple approximate criterion is derived for the estimation of the importance of energy degradation during plasma buildup in a DCX type machine. Next, there is derived the steady-state ion energy distribution for a case in which energy losses are to electrons at a given temperature and particle losses are by charge exchange. The distribution function is used to compute loss rate, upper critical current, ionization rate, and other functions of interest. Quantitative application is made to DCX-2 under various conditions of operation of carbon and deuterium arcs.
Date: September 30, 1960
Creator: Rose, D. J.
Object Type: Report
System: The UNT Digital Library
Thermal Characteristics of Fluid Flow in Pipes (open access)

Thermal Characteristics of Fluid Flow in Pipes

An investigation is made to determine the adequacy of presently used analog circuits in solving dynamic fluid flow heat transfer equations. A mathematical analysis is made of dynamic heat transfer in pipes with zero losses, with losses proportional to pip temperature, and with heat inputs. The results of this analysis are compared with analog results by means of generalized temperature versus time graphs. The analog circuit is found to be adequate for most conditions, but sometimes requires modification when heat inputs are considered.
Date: September 13, 1960
Creator: Hinton, D. B.
Object Type: Report
System: The UNT Digital Library
Preliminary Analog Computer Study of the Small EGCR In-Pile Loops (open access)

Preliminary Analog Computer Study of the Small EGCR In-Pile Loops

The ORNL analog computer was used to simulate four widely different experiment conditions in the small EGCR in-pile loops. Various control and safety systems were evaluated in each case. Curves are included which show the response to postulated accidents and component failures. The results indicate that one standard control and safety system will probably be adequate for a wide variety of test conditions.
Date: September 21, 1960
Creator: Ball, S. J. & Beasley, E. G.
Object Type: Report
System: The UNT Digital Library
Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source (open access)

Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source

The solution of the monoenergetic Boltzmann equation in an infinite homogeneous, nonmultiplying medium with linearly anisotropic scattering and an isotropic plane source is given and compared with the corresponding solution for isotropic scattering. The effective source strength for the asymptotic flux turns out to be the same as that for isotropic scattering to first order in Σa/Σ.
Date: September 6, 1960
Creator: Inonu, Erdal
Object Type: Report
System: The UNT Digital Library
University of Illinois, Graduate College, Digital Computer Laboratory, Technical Progress Report (open access)

University of Illinois, Graduate College, Digital Computer Laboratory, Technical Progress Report

The report includes summary reports in five areas (1) High-speed computer program, (2) Mathematical methods, (3) ILLIAC use and operations, (4) IBM 650 use and operation, and (5) General laboratory information.
Date: September 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Radioactive Waste Disposal and Miscellaneous Work : Annual Report for Calendar Year 1956 (open access)

Radioactive Waste Disposal and Miscellaneous Work : Annual Report for Calendar Year 1956

An annual report is given on the operation and costs of waste-disposal facilities at ORNL laboratories and operating buildings in the Bethel Valley area. The operations of the hot-chemical and metal-waste systems, the process-waste system, and the radioactive-gas-disposal system which utilized the 250-ft stack located in the Radioisotope area are discussed. The miscellaneous operations which include the SS (source and special nuclear) material control, SS material recovery, off-shift service for research divisions, water demineralization plant operations, and hydrogen liquefaction are included. However, the disposal of cooling water from LITR, off-gases from the Hot Pilot Plant, and the ORNL Graphite Reactor building are not covered by the report.
Date: September 11, 1957
Creator: Seagren, H. E. & Witkowski, E. J.
Object Type: Report
System: The UNT Digital Library
Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962 (open access)

Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962

This is the second quarterly report on the work done under Contract AT(04-3)-189, Project Agreement No. 27. The results reported here have to do primarily with the loss in a rectangular (1/2" x 1-3/4") channel in the horizontal orientation, without contraction-expansion inserts.
Date: September 12, 1962
Creator: Janssen, E. & Kervinen, J. A.
Object Type: Report
System: The UNT Digital Library
Radioactivation Analysis (open access)

Radioactivation Analysis

The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radiation and half-life, it is possible, through radiochemical measurements following radioactivation, to devise a method of analysis which is very specific for particular elements. Whenever necessary, the radioisotope is separated by chemical means and its radioactivity is then measured by some type of radiation counter.
Date: September 22, 1961
Creator: Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library
Section 9.0 to Status Report on the Disposal of Radioactive Wastes (open access)

Section 9.0 to Status Report on the Disposal of Radioactive Wastes

Section 9.0 is the "Chemical Processes for Fission Product Concentration, Removal or Fixation" section of the Status Report on the Disposal of Radioactive Wastes. The report is divided into four areas: (1) Introduction; (2) Summary of waste processes; (3) Concept of a multipurpose waste processing facility; and (4) Details of some of the waste processes.
Date: September 3, 1957
Creator: Culler, Floyd L., Jr.
Object Type: Report
System: The UNT Digital Library