Resource Type

Abscissas and Weights for Guassian Quadrature For N=2 to 100, and N-125, 150, 175, 200 (open access)

Abscissas and Weights for Guassian Quadrature For N=2 to 100, and N-125, 150, 175, 200

The abscissas and weights for Gaussian Quadrature of order N = 2 to 100,and N = 125, 150, 175, and 200 are given. The abscissas are given to twenty-four places and the error is estimated to be no more than 1 unit in the last place. The weights are given to twenty-three places and the error is estimated to be no more than 1 unit in the last place.
Date: December 28, 1966
Creator: Love, Carl H.
Object Type: Report
System: The UNT Digital Library
Acceleration of Deuterons or Alpha Particles in the AGS (open access)

Acceleration of Deuterons or Alpha Particles in the AGS

The magnetic field of the AGS ring can contain particles of magnetic rigidity about 34 Bv/c. This includes not only protons of kinetic energy 33 Bev, but also 32 Bev deuterons, 64 Bev alpha particles, and conceivably heavier nuclei such as 188 Bev carbon nuclei. It will be shown in this paper that such nuclei can be injected and accelerated in the AGS if some rather small modifications are made in the injection and acceleration systems. What physics could be done with such beams? Several types of experiments may be suggested. In the first place, since the deuteron is a rather loosely bound combination of a neutron and a proton, it is likely to break up when it hits a target nucleus (stripping reaction). In a considerable fraction of the collisions the neutron will go straight on with essentially unchanged energy (half the deuteron energy). Therefore, with an internal target bombarded by 30 Bev deuterons one should obtain an intense, rather well collimated and monochromatic beam of 15 Bev neutrons in the forward direction.
Date: December 28, 1962
Creator: Courant, E. D.
Object Type: Report
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963) (open access)

Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: December 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Object Type: Report
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962 (open access)

Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962

Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
Date: December 1, 1962
Creator: Rider, B. F.; Ruiz, C. P. & Peterson, J. P.
Object Type: Report
System: The UNT Digital Library
Advanced Test Reactor: Final Shielding Design Report (open access)

Advanced Test Reactor: Final Shielding Design Report

From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Date: December 1963
Creator: Howard, J. O. & Jacks, G. M.
Object Type: Report
System: The UNT Digital Library
Aeroradioactivity Survey and Areal Geology of the Savannah River Plant Area, South Carolina and Georgia (ARMS-I) (open access)

Aeroradioactivity Survey and Areal Geology of the Savannah River Plant Area, South Carolina and Georgia (ARMS-I)

Report regarding an airborne radioactivity survey that took place in the 10,000 square mile area near Augusta, Georgia. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: December 1960
Creator: Schmidt, Robert G.
Object Type: Report
System: The UNT Digital Library
After Shutdown Heating in the HFIR (open access)

After Shutdown Heating in the HFIR

After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.
Date: December 29, 1960
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents (open access)

Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
Object Type: Report
System: The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium (open access)

Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium

Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date: December 27, 1960
Creator: Gaitanis, M. J.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report, September 30, 1968 (open access)

Analytical Chemistry Division Annual Progress Report, September 30, 1968

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
Date: 1964-12~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
Object Type: Report
System: The UNT Digital Library
An Analytical Model for Predicting Cross-Country Vehicle Performance, Appendix B: Vehicle Performance in Lateral and Longitudinal Obstacles (Vegetation), Volume 1: Lateral Obstacles (open access)

An Analytical Model for Predicting Cross-Country Vehicle Performance, Appendix B: Vehicle Performance in Lateral and Longitudinal Obstacles (Vegetation), Volume 1: Lateral Obstacles

First part of an appendix that accompanies a study meant to develop a model for predicting the cross-country performance of military vehicles in various conditions. This volume describes a segment of tests to determine the ability of vehicles to negotiate lateral obstacles (e.g., trees, boulders, holes, mounds, etc.).
Date: December 1968
Creator: Blackmon, Claude A. & Stoll, Jack K.
Object Type: Report
System: The UNT Digital Library
Anion Exchange of Neptunium in Nitrate Solutions (open access)

Anion Exchange of Neptunium in Nitrate Solutions

Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."
Date: December 1960
Creator: Burney, Glenn A.
Object Type: Report
System: The UNT Digital Library
Antiproton-Nucleon Cross Sections From 0.5 To 1.0 Bev (open access)

Antiproton-Nucleon Cross Sections From 0.5 To 1.0 Bev

Antiproton-production and nucleon-interaction cross sections were investigated for antiprotons in the energy range 0.5 to 1.0 Bev. The antiprotons were distinguished from other particles produced at the Bevatron by a system of scintillation- and velocity-selecting Cerenkov counters. The excitation function and momentum distribution were recorded for antiproton production in carbon and compared with statistical model expectations.
Date: December 12, 1961
Creator: Elioff, Tommy; Agnaw, Louis; Chamberlain, O. (Owen); Steiner, Herbert M.; Wiegand, Clyde (Clyde Edward), 1915-1996 & Ypsilantis, Tom
Object Type: Report
System: The UNT Digital Library
The Application of Data Processing Techniques to a Maintenance Work Control Program (open access)

The Application of Data Processing Techniques to a Maintenance Work Control Program

Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
Date: December 18, 1963
Creator: Westbrook, J. D.
Object Type: Report
System: The UNT Digital Library
Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres (open access)

Application of the Variational Method to the Calculation of the Time Dependence of the Neutron Flux in Small Pulsed Slabs, Cylinders and Spheres

The variational method is applied to the monoenergetic time dependent transport equation to obtain a simple relation for the asymptotic decay constant in small pulsed assemblies. The results indicate that flat trial functions may be a reasonable representation of the flux distributions in the thin slab limit. This approach is superior to many of the usual transport approximations.
Date: December 16, 1963
Creator: Judge, F. D. & Daitch, Paul B. (Paul Bernard), 1925-
Object Type: Report
System: The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor (open access)

Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date: December 23, 1960
Creator: Wick, E. A. & Heestand, R. L.
Object Type: Report
System: The UNT Digital Library
Barrier Attenuation of Air-Scattered Gamma Radiation (open access)

Barrier Attenuation of Air-Scattered Gamma Radiation

Report of a study that "was conducted to determine the attenuation provided by vertical and horizontal barriers exposed only to skyshine radiation from cobalt-60 and cesium-137 sources. Materials of steel, aluminum, concrete, and wood were used as barriers" (p. 5).
Date: December 1964
Creator: Burson, Z. G. & Summers, R. L.
Object Type: Report
System: The UNT Digital Library
Bounce III (open access)

Bounce III

BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date: December 15, 1960
Creator: Kerr, B. A.
Object Type: Report
System: The UNT Digital Library
The Boundary Layer Between a Plasma and a Magnetic Field - I (open access)

The Boundary Layer Between a Plasma and a Magnetic Field - I

"The problem of a steady boundary layer or sheath between a plasma and a magnetic field is considered. A self-consistent transition layer is found which joins a uniform magnetic field at plus infinity with a collisionless field-free plasma region with arbitrary velocity distribution at minus infinity, i.e., a magnetic field profile is found such that the exact particle orbits in this field produce a current which gives rise to this field. An interesting feature of the solution is that, with any nonsingular velocity distribution at minus infinity, the magnetic field the plasma extends to infinity, exponentially attenuated, into the magnetic field region. The scale of length is the Larmor radius. Electric fields arising from charge separation in the case of particles of different mass are ignored."
Date: December 28, 1960
Creator: Grad, Harold, 1923-
Object Type: Report
System: The UNT Digital Library
A Cascade Impactor Operating at Low Volumetric Flow Rates (open access)

A Cascade Impactor Operating at Low Volumetric Flow Rates

Report describing a five-stage cascade impactor, which has four impactor stages in which round jets are used and a filter stage. The method of calibrating the device is described. The significance of the collection efficiency and wall losses with respect to sampling for mass distributions is discussed.
Date: December 1962
Creator: Mercer, T. T.; Tillery, M. I. & Ballew, C. W.
Object Type: Report
System: The UNT Digital Library
Centrifugal Creep Test Machine Evaluation Program: Final Report (open access)

Centrifugal Creep Test Machine Evaluation Program: Final Report

Abstract: A centrifugal creep test machine was evaluated for in-pile creep use.
Date: December 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Characteristics of U.S. Rice Fields and Their Effects on Ground Mobility (open access)

Characteristics of U.S. Rice Fields and Their Effects on Ground Mobility

"The primary objective of this study was to obtain information on the environmental characteristics of rice fields in the United States and the effect of these characteristics on ground mobility for comparison with similar characteristics of rice fields in Southeast Asia as data from the latter become available" (p. vii).
Date: December 1965
Creator: Kennedy, James Garland & Rush, Edgar S.
Object Type: Report
System: The UNT Digital Library
Civil Defense Research Project Annual Progress Report: March 1966 - March 1967 (open access)

Civil Defense Research Project Annual Progress Report: March 1966 - March 1967

Report containing the results of Oak Ridge National Laboratory's research relating to civil defense.
Date: December 1967
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
The Class of Shocks With Uniform Pressure (open access)

The Class of Shocks With Uniform Pressure

If a piston with constant velocity moves into a shock tube containing material at rest and at uniform density, the result is well known and trivial. The shock propagates with uniform speed, the state and speed of the material behind the shock is constant. One can ask if similar flows exist for cylindrical of spherical symmetry. Quickly one rules out the possibility of a solution which retains all the properties of this trivial solution. One asks if there are any solutions such that the material behind the shock is not accelerated. Indeed, there are. In the following, it is shown that for a y-law gas, there is a family of densities such that if a piston moves into the material with uniform velocity, the material behind the shock is not accelerated. Further, these are the only densities with this property. In the case of planar symmetry, the trivial case mentioned above is a member of the family, as is to be expected.
Date: December 1963
Creator: Hardy, John W.
Object Type: Report
System: The UNT Digital Library