1706-KER Coolant Test Facility Operations Manual (open access)

1706-KER Coolant Test Facility Operations Manual

This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
Date: January 23, 1958
Creator: Dulin, R. V.
Object Type: Report
System: The UNT Digital Library
An Abrasive Cutoff Machine for Metallurgical Research on Radioactive Materials (open access)

An Abrasive Cutoff Machine for Metallurgical Research on Radioactive Materials

An abrasive cutoff machine design, based upon a previous model, (1) was undertaken to provide for the sampling of radioactive material. the design objective was; first, to provide samples for metallographic examination, second, to provide samples for physical and mechanical property testing, and, third, to meet the following design requirements: 1. Remote operation. 2. Airborne contamination control. 3. Radioactive waste collection. 4. Remote maintenance.
Date: January 5, 1957
Creator: Boyd, C. L.
Object Type: Report
System: The UNT Digital Library
Aircraft Reactor Test Hazards Summary Report (open access)

Aircraft Reactor Test Hazards Summary Report

The successful completion of a program of experiments, including the Aircraft Reactor Experiment (ARE), has demonstrated the high probability of producing militarily useful aircraft nuclear power plants employing reflector-moderated circulating-fuel reactors. Consequently, and accelerated program culminating in operation of the Aircraft Reactor Test (ART) is under way. In order to adhere to the compressed schedule of the accelerated program, it is essential that the Atomic Energy Commission approve the 7500 Area in Oak Ridge as the test site by February15, 1955. This report summarizes the hazards associated with operating the contained 60-Mv reactor of the ART at the proposed Oak Ridge test site.
Date: January 19, 1955
Creator: Cottrell, W. B.; Ergen, W. K.; Fraas, A. P.; McQuilkin, F. R. & Meem, J. L.
Object Type: Report
System: The UNT Digital Library
The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes (open access)

The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
Object Type: Report
System: The UNT Digital Library
An Alpha Energy Analyzer (open access)

An Alpha Energy Analyzer

This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.
Date: January 27, 1956
Creator: Campbell, Don A.
Object Type: Report
System: The UNT Digital Library
Ames Laboratory Quarterly Summary Research Report: Octoer - December 1950 (open access)

Ames Laboratory Quarterly Summary Research Report: Octoer - December 1950

A report about investigations of several binary alloy systems of thorium. Some of these alloys containing lead, molybdenum and tin have been prepared in the tungsten arc furnace.
Date: January 30, 1951
Creator: Dreeszen, W. E.
Object Type: Report
System: The UNT Digital Library
Analysis of Lid Tank Neutron Data for Lead and Iron (open access)

Analysis of Lid Tank Neutron Data for Lead and Iron

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.
Date: January 5, 1951
Creator: Podgor, S.
Object Type: Report
System: The UNT Digital Library
Analysis of Spurious Modes in Magnet Power Supply (open access)

Analysis of Spurious Modes in Magnet Power Supply

"The resonant frequencies of the magnet power supply are investigated. It is found that there are eleven resonant modes in addition to the desired mode of operation with six additional resonant frequencies. From measurements of the choke model, it appears that the frequencies of some of the spurious modes may lie in the same range as the desired mode of operation."
Date: January 3, 1958
Creator: Dekleva, J. & Robinson, K. W.
Object Type: Report
System: The UNT Digital Library
The Application of Pulsed Neutron Sources to Criticality Measurements (open access)

The Application of Pulsed Neutron Sources to Criticality Measurements

Abstract: Experimentally measured promp-neutron decay constants for sub-critical systems are of considerable value as normalization data for calculations of prompt-neutron time constants. A method of measuring these decay constants with a pulsed neutron source, neutron detector and multi-channel time-delay analyzer has been developed and used on a number of fast-spectrum subcritical systems. An analysis of this method based on the one-energy group, one-delayed-neutron group reactor kinetic equations is presented and discussed. The curve of neutron flux versus time predicted by the kinetic equations is compared with the observed curve obtained with a 13.1-cm. diam. enriched-uranium sphere to indicate the application and limitations of the analysis.
Date: January 30, 1957
Creator: Passell, Lawrence; Bengston, Joel & Blair, Donald C.
Object Type: Report
System: The UNT Digital Library
APPR-1 Type Absorber Rod Irradiation Test -- Irradiation Request ORNL MTR-29 (open access)

APPR-1 Type Absorber Rod Irradiation Test -- Irradiation Request ORNL MTR-29

In order to evaluate the behavior of an APPR type absorber rod, an irradiation test program has been established. Approximately 21 more samples are planned for testing under this request. The request proposes testing a full size APPR-1 type control rod in the MTR. The objective of the test is to better evaluate the neutron absorbing material proposed for the APPR-1 control rod.
Date: January 4, 1957
Creator: Gross, E. E. & Schaffter, L. D.
Object Type: Report
System: The UNT Digital Library
The Approximation with Anisotropic Effects for Cylindrical Geometry (open access)

The Approximation with Anisotropic Effects for Cylindrical Geometry

The method of spherical harmonic tensors developed Mark for solving the Boltzmann transport equation in isotropic media is herein extended to anisotropic media for cylindrical geometry. A formal solution is given for the case of two concentric cylindrical media, A and B, but no numerical work has yet been done. The following treatment differs from a similar one by the H. K. Ferguson Co. in that the external medium B is assumed to be both a neutron absorber and finite in extent rather than a non-absorber and infinite in extent.
Date: January 22, 1953
Creator: Fleck, J.
Object Type: Report
System: The UNT Digital Library
Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium (open access)

Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium

Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are reported for uranium-0, 5, 10, 15, and 20 w/o zirconium alloys subjected subjected to 600 F water.
Date: January 7, 1957
Creator: Grieser, Daniel R. & Simons, Eugene M.
Object Type: Report
System: The UNT Digital Library
Average Fission Cross Section U238 for Fission Neutrons (open access)

Average Fission Cross Section U238 for Fission Neutrons

By means of measurements with a double ionization chamber, the average fission cross section of U238 for neutrons from the fission of U235 was determined in terms of v, the average number of neutrons per fission of U235. the number of fission of U238 was measured in one of the ionization chambers while the number of fissions from the fission neutron source of U235 was measured in the other chamber. In the nine runs made to determine the cross section, a variety of different methods was used to determine the number of fissions and the mass of U238.
Date: January 1953
Creator: Leachmanm R. B. & Schmitt, H. W.
Object Type: Report
System: The UNT Digital Library
Behavior, a Balanced Network of Chemical Transformations (Biokinetics) (open access)

Behavior, a Balanced Network of Chemical Transformations (Biokinetics)

Abstract. While the concept of a biological system as a balanced network of chemical transformations is not a new one, experimental definition of specific systems has been lacking. This paper defines theoretically and experimentally a number of such networks and their behavior and response to some limited environmental changes.
Date: January 13, 1954
Creator: Bradley, D.F. & Calvin, M.
Object Type: Report
System: The UNT Digital Library
Betatron Oscillations and Equilibrium Orbits in Terms of Amplitude and Phase Functions (open access)

Betatron Oscillations and Equilibrium Orbits in Terms of Amplitude and Phase Functions

"Formulas are given to express the general particle trajectory and the equilibrium orbit for a slightly disturbed synchrotron in terms of the amplitude and phase functions for the ideal machine. If these functions are known, orbit computations can be carried out by simple integration procedures. The formalism is expected to be useful especially for considerations such as beam alignment or generation of an external electron beam. Some equations given earlier are repeated for completeness."
Date: January 7, 1958
Creator: Steffen, K. G.
Object Type: Report
System: The UNT Digital Library
Bibliography on High Pressure Systems and High Pressure-High Temperature Systems : Techniques, Apparatus and Experimental Data (open access)

Bibliography on High Pressure Systems and High Pressure-High Temperature Systems : Techniques, Apparatus and Experimental Data

From preface: The following bibliography on high pressure-high temperature, and high pressure, is the result of an investigation into the equipment and experimental technique needed to increase the density of powdered compounds, especially those compounds which possess a high vapor pressure of hydrogen at moderate temperature and pressure.
Date: January 10, 1958
Creator: Lakner, John F.
Object Type: Report
System: The UNT Digital Library
A Brief Course in Radiation Dosimetry and its Application to Personnel Protection (open access)

A Brief Course in Radiation Dosimetry and its Application to Personnel Protection

By radiation dosimetry, we will mean the determination of the energy deposited per unit mass of irradiated material by ionizing radiation. Usually the material of interest in tissue and the results are to be applied to a radiobiological experiment, a radiotherapy treatment, or the protection of personnel from radiation hazards. The same methods, however, are applied to such engineering problems as the production of heat by reactor radiations, the use of radiation in chemical reactions or food processing, etc.
Date: January 23, 1958
Creator: Roesch, Wm. C.
Object Type: Report
System: The UNT Digital Library
Calculated Pressure Drop In the 1706-KER Loop (open access)

Calculated Pressure Drop In the 1706-KER Loop

The purpose of this report is to provide calculated liquid flow pressure drop data for the 1706-KER recirculation loops.
Date: January 31, 1956
Creator: Sebade, D. E.
Object Type: Report
System: The UNT Digital Library
Calculation of Shield Induced Gamma Radiation Escaping Through Openings in a Biological Shield -- Application to the HRT (open access)

Calculation of Shield Induced Gamma Radiation Escaping Through Openings in a Biological Shield -- Application to the HRT

A method was developed for calculating shield induced gamma radiation escaping through openings in a biological shield. The method was applied to the HRT and the results indicated that the contribution to the dose from induced activity in the HRT shield was around 0.1 r/hr and was insignificant in comparison to to other mechanisms contributing to the escape of gamma rays through shield openings.
Date: January 11, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
Object Type: Report
System: The UNT Digital Library
Calculation of Transport Cross-Sections of Uranium (open access)

Calculation of Transport Cross-Sections of Uranium

In recent months, experiments investigating the total, non-elastic, transport, etc., cross-sections of U-238 have been performed. It is the purpose of this memo to examine these data and to obtain from them information which will be of use in refinements pile calculations. In cases, e.g. transport cross-sections, where experimental data do not suffice, the theory developed pertaining to the continuum model of the nucleus has been depended upon. One of the fundamental requirements of this model is that the spacings of the energy levels in the compound nucleus are small compared to their widths and that consequently many levels are excited by the incoming particles. As a result there are many more modes of decay and the continuum model is an average over these levels.
Date: January 9, 1953
Creator: Oleksa, S.
Object Type: Report
System: The UNT Digital Library
Carbon Steel in High Temperature Water (open access)

Carbon Steel in High Temperature Water

Resistance of carbon steel to corrosion in oxygenated high-temperature (250C) water was unexpectedly good at high oxygen concentration. Pertinent literature, critically examined, and toroid experiments indicted that at low oxygen concentration attack did increase with concentration, but as oxygen concentration was sufficiently increased, more protective films were formed on the metal. Some corrosion factors in the application of carbon steel to nuclear reactors systems are discussed.
Date: January 31, 1957
Creator: Moore, G. E.
Object Type: Report
System: The UNT Digital Library
Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries (open access)

Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries

Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date: January 29, 1957
Creator: Morse, L. E.
Object Type: Report
System: The UNT Digital Library
A Cement Base for the Hot Filament Mass Spectrometer Source (open access)

A Cement Base for the Hot Filament Mass Spectrometer Source

The following document is meant to inform the reader on the makings of a cement base for the hot filament mass spectrometer source as part of a publication in the review of scientific instruments, "Laboratory and Shop Notes".
Date: January 17, 1952
Creator: Hand, John E.
Object Type: Report
System: The UNT Digital Library
The Characteristics of Bismuth Fission Induced by 340 Mev Protons (open access)

The Characteristics of Bismuth Fission Induced by 340 Mev Protons

Bismuth metal was irradiated with 340 Mev protons in the circulating beam of the 184-inch Berkeley cyclotron. Nuclides formed as fission products during the course of the bombardment were separated and studied through the use of radiochemical techniques.
Date: January 1953
Creator: Biller, William Frederick
Object Type: Report
System: The UNT Digital Library