States

9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090 (open access)

9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.
Date: October 28, 1960
Creator: Stone, Stuart P.
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
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.
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.
System: The UNT Digital Library
Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates (open access)

Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates

The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.
Date: June 28, 1960
Creator: Aaland, Kristian
System: The UNT Digital Library
Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR (open access)

Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR

An analog simulation is made of the HRP in-pile slurry loop in the LITR. The radiolytic gas pressure in the pressurizer is determined. This pressure is a result of the generation of radiolytic gas in the loop core. A graphical result is obtained showing the effect of catalyst activity and pressurizer flow rate on the pressure rise from radiolytic gas. The thermal behavior of the system is studied, and the response to various controller settings is predicted. Controller settings very near optimum for the actual process were recommended from the analog study,
Date: November 28, 1960
Creator: Hinton, D. B.
System: The UNT Digital Library
Applications for Lanthanon Oxides and Other Compounds in the Ceramic Industry (open access)

Applications for Lanthanon Oxides and Other Compounds in the Ceramic Industry

Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.
Date: January 28, 1960
Creator: Ploetz, G. L.
System: The UNT Digital Library
Bibliography of Temperature Measurement: July 1960 to December 1965 (open access)

Bibliography of Temperature Measurement: July 1960 to December 1965

Report combining National Bureau of Standards Monograph 27 with the references given in Supplement 1 (May 13, 1963) and issued as a single publication to assist users of this material. References concern the field of temperature measurement. These references were collected from two general sources: Scientific and technical literature and government reports. References are divided into a number of categories based on the type of instrument used. Some references to calibration of instruments and to scientific theories upon which temperature measurement is based are also presented.
Date: April 28, 1967
Creator: Olsen, Lief O. & Halpern, Carl
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-
System: The UNT Digital Library
BWR Reference Design for PL-3 (open access)

BWR Reference Design for PL-3

Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and training program outline.
Date: February 28, 1962
Creator: Humphries, G. E.
System: The UNT Digital Library
Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing (open access)

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
System: The UNT Digital Library
Development of Pressures Tubing for the Plutonium Recycle Test Reactor (open access)

Development of Pressures Tubing for the Plutonium Recycle Test Reactor

Pressurized water nuclear reactors may be designed based upon either of two concepts: (1) pressure vessel, wherein the entire core is placed in a large, high strength fuel channels within a low pressure container. The Plutonium Recycle Test Reactor is a pressure tube type reactor. Selection of this basic type of pressurized water reactor depended to an appreciable extent upon the availability of suitable pressure tubing.
Date: April 28, 1960
Creator: Riches, J. W.
System: The UNT Digital Library
Disposition of Radiation Products and Energy Transfer in Radiobiological Processes (open access)

Disposition of Radiation Products and Energy Transfer in Radiobiological Processes

Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.
Date: March 28, 1962
Creator: Augenstine, L. G.
System: The UNT Digital Library
The Effect of Aneuploidy Upon the Chromosome Number of Succeeding Generations of Tetraploid Maize (open access)

The Effect of Aneuploidy Upon the Chromosome Number of Succeeding Generations of Tetraploid Maize

Technical report outlining the effects of chromosomal abnormalities in tetraploid Argentine flint maize pollination, and subsequent generations.
Date: March 28, 1962
Creator: Shaver, Donald L.
System: The UNT Digital Library
Electron Requirements of Bonds in Metal Borides (open access)

Electron Requirements of Bonds in Metal Borides

From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."
Date: May 28, 1962
Creator: Johnson, Robert W. & Daane, A. H. (Adrian Hill), 1919-
System: The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants (open access)

Evaluation and Design Heavy Water Moderated Power Reactor Plants

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.
Date: April 28, 1960
Creator: unknown
System: The UNT Digital Library
Evidence For a T = 0 Resonance in the Z[ ] System (open access)

Evidence For a T = 0 Resonance in the Z[ ] System

In previous letters we have reported a Av resonance, called Y*1, observed through the study of the interaction of 1.15-Bev/c K* mesons in hydrogen in the Lawrence Radiation Laboratory 15-in. bubble chamber. We now wish to report the results of the study of the three reactions [formula](1), [formula](2) and [formula](3).
Date: April 28, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W., 1911-1988; Eberhard, Phillippe; Good, Myron L.; Graziano, William; Ticho, Harold K., 1921-2020 et al.
System: The UNT Digital Library
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F (open access)

Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F

Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date: February 28, 1961
Creator: McDonald, J. S.
System: The UNT Digital Library
Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963 (open access)

Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963

From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
Date: October 28, 1963
Creator: unknown
System: The UNT Digital Library
Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3 (open access)

Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
System: The UNT Digital Library
Geologic Map of Pahute Mesa, Nevada Test Site, Nye County, Nevada (open access)

Geologic Map of Pahute Mesa, Nevada Test Site, Nye County, Nevada

This report summarizes the geological features of the Pahute Mesa map in the Nevada Test Site.
Date: August 28, 1967
Creator: Orkild, Paul P. & Sargent, Kenneth A.
System: The UNT Digital Library
HAPO IB Fission Product Shipping Cask Design Evaluation Report (open access)

HAPO IB Fission Product Shipping Cask Design Evaluation Report

As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In addition, the development of strontium-90 as a major product requires increased flexibility in the utilization of these casks.
Date: December 28, 1962
Creator: Smith, C. W.
System: The UNT Digital Library
Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures. (open access)

Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
System: The UNT Digital Library
Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1 (open access)

Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1

The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.
Date: December 28, 1962
Creator: Hackney, M. R. & Ruiz, C. P.
System: The UNT Digital Library