Resource Type
Serial/Series Title
Argonne National Laboratory Reports
34
Atomic Energy Commission Reports
33
Oak Ridge National Laboratory Reports
16
TID
16
AEC research and development report
11
ORNL (Series)
11
United States Geological Survey Reports
10
GJBX
8
Homogeneous Reactor Project Quarterly Progress Report
8
National Bureau of Standards Reports
7
51 More
Country
States
Decade
Month
114 Matching Results
Results open in a new window/tab. Unexpected Results? Search the Catalog Instead.
Results:
1 - 24 of
114
next
Evaluation of the Lead-Alpha (Larsen) Method for Determining Ages of Igneous Rocks
A report about analyzing the age of igneous rock using its lead-alpha activity.
Date:
1959
Creator:
Gottfried, David; Jaffe, Howard W. & Senftle, Frank E.
Object Type:
Report
System:
The UNT Digital Library
Lead-Alpha Age Determinations of Granitic Rocks from Alaska
Abstract: "Lead-alpha activity age determinations were made on zircon from seven granitic rocks of central and southeastern Alaska. The results of the age determinations indicate two periods of igneous intrusion, one about 95 million years ago, during the Cretaceous period, and another about 53 million years ago, during the early part of the Tertiary. The individual ages determined on zircon from 2 rocks from southeastern Alaska and 1 from east-central Alaska gave results of 90, 100, and 96 million years; those determined on 4 rocks from central Alaska gave results of 47, 56, 58, and 51 million years."
Date:
March 1957
Creator:
Matzo, J. J.; Jaffe, H. W. & Waring, C. L.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Mechanisms of Heat Treatment of Zirconium-Base Alloys : Status Report, July 1, 1955 - February 29, 1956
The kinetics of transformation of zirconium binary alloys is being pursued. Mechanical property variation as a function of transformation if also being investigated. Zirconium-tin and zirconium-titanium alloys transform very rapidly when quenched from the beta field. These alloys have, generally speaking, been demonstrated to be not amenable to heat treatment in the normal sense of the word. Eutectoid alloys, principally zirconium-molybdenum alloys, have shown a definite response to heat treatment in terms of mechanical property variation. An embrittling agent, probably "omega" phase, is suspect at this time for the brittleness observed in certain molybdenum alloys and the very high hardness levels reached in other alloys such as zirconium-niobium and zirconium-thorium. Work to establish the existence of omega phase is in progress and, it is hoped, suggestions for avoiding the brittle condition associated with it will be forthcoming.
Date:
March 15, 1956
Creator:
Domagala, R. F. & Levinson, David W.
Object Type:
Report
System:
The UNT Digital Library
Operational Health Physics Training
This revised publication updates a previous report (ANL-7291) initially published in 1965, entitled Radiation Safety Technician Training Course which was intended to complement on-the-job monitoring training for Health Physics Technicians. Sections include basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of alpha, beta, gamma, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units).
Date:
June 1992
Creator:
Moe, H. J. & Vallario, Edward J.
Object Type:
Report
System:
The UNT Digital Library
Mechanical Properties of Zircaloy-2 - Niobium - Oxygen Alloys
Introduction: The effects of temperature on the mechanical properties of Zircaloy-2 containing up to 7.5 wt % niobium and 3500-ppm oxygen were studied and are presented herein.
Date:
January 15, 1963
Creator:
Bibb, A. E. & Fascia, J. R.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During October, 1955
A report about uranium alloys, fuel element development,, zirconium-uranium alloys, zirconium erosion, and the development of reactor materials.
Date:
November 1, 1955
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Lode Deposits of the Fairbanks District, Alaska
From abstract: To help the mining industry of Alaska and to assist in the development of the mineral resources of the Territory have been the prime motives of the Geological Survey's investigations in Alaska during the past 35 years, in which nearly one half of the Territory has been covered by its reconnaissance and exploratory surveys. It was natural, therefore, that the Alaska Railroad, when it undertook intensive consideration of the problem of finding tonnage that would increase its revenues, should look to the Geological Survey to supply technical information as to the known mineral deposits along its route and to indicate what might be done to stimulate a larger production of minerals and induce further mining developments and prospecting that would utilize its service.
Date:
1933
Creator:
Hill, James M.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report January, February and March, 1956
The EBWR loading requires a total of 888 plates. It is anticipated that approximately 1000 plates will have to be produced to obtain the number of acceptable plates required for the loading. To the end of this quarter, 568 cladding billet cores acceptable with respect to chemical composition and physical soundness had been cast; this number represents 78% of the total number of cores cast. Approximately 75% of the Zircaloy-II stock required has been rolled, and about 55% of the cladding components required have been finished. The anticipated number of 495 cladding billets required for the thin (0.210") natural and enriched plates have been assembled, welded, sealed, and jacketed in steel. A total of 310 cladding billets have been rolled to fuel plates; of this number, 142 have been completely finished, and the remaining 168 are in the finish processing stages. The stability of the equipment for measuring the clad thickness of EBWR fuel plates has been improved by placing the phototube and the anthracene scintillator crystals in an insulated box with a temperature regulation of the order of 0.1°F.
Date:
June 1956
Creator:
Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Object Type:
Report
System:
The UNT Digital Library
An evaluation of data on zirconium-uranium alloys
Report describing the literature relative to zirconium-uranium alloys. The available data related to zirconium-uranium alloys is analyzed in an attempt to understand the behavior and nature of the alloy. Other aspects of zirconium-uranium alloys are discussed in the report.
Date:
1955
Creator:
Rough, Frank A.
Object Type:
Report
System:
The UNT Digital Library
Shippingport Atomic Power Station : Monthly Operating Report, November 1959
The Monthly Operating Report is divided into seven major sections: Summary of Report, Station Activity Schedule, Operations, maintenance, Refueling, Test Program and Training Program.
Date:
1959
Creator:
Oldham, G. M.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During May, 1956
A report about mechanical properties of dilute uranium alloys are being investigated in an effort to develop a high-strength alloy for fuel elements. Elevated temperature tensile tests were made on two dilute uranium-aluminum alloys, and several ternary alloys were arc melted.
Date:
June 1, 1956
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Improved Zirconium Alloys : Summary Report, April 1, 1960 - January 31, 1961
Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium purity and heat treatment for improvement of corrosion properties are proceeding. Hydrogen pickup and mechanical properties will be used as acceptability tests on promising compositions."
Date:
February 28, 1961
Creator:
Weinstein, Daniel; Holtz, F. C. & Van Thyne, R. J.
Object Type:
Report
System:
The UNT Digital Library
A Survey of Some Los Alamos County Canyons for Radioactive Contamination, Spring 1953 to Spring 1955
Abstract: This document is a survey analysis of soil samples from Los Alamos, Pueblo, Bayo, and Mortandad canyons to determine the presence and activities of radioactive contaminants. Also included are the results of analyses of a few samples of grass and of surface water. This survey covers the period from spring 1953 to spring 1955.
Date:
April 1956
Creator:
Dodd, Aubrey O.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During February, 1956
A report about aluminum-clad fuel elements, fuel-element development, zirconium uranium alloys, corrosion of zirconium, and reactor material development.
Date:
March 1, 1956
Creator:
Dayton, Russell W.
Object Type:
Report
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: May-July 1960
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
1960
Creator:
Oak Ridge National Laboratory
Object Type:
Report
System:
The UNT Digital Library
FX2-TH : A Two-Dimensional Nuclear Reactor Kinetics Code with Thermal-Hydraulic Feedback
FX2-TH is a two-dimensional, time-dependent nuclear reactor kinetics program with thermal and hydraulic feedback. The neutronics model used is multi-group neutron diffusion theory. The following geometry options are available: x, r, x-y, r-z, theta-r, and triangular. FX2-TH contains two basic thermal and hydraulic models: a simple adiabatic fuel temperature calculation, and a more detailed model consisting of an explicit representation of a fuel pin, gap, clad, and coolant. FX2-TH allows feedback effects from both fuel temperature (Doppler) and coolant temperature (density) changes. FX2-TH will calculate a consistent set of steady state conditions by iterating between the neutronics and thermal-hydraulics until convergence is reached. The time-dependent calculation is performed by the use of the improved quasistatic method. A disk editing capability is available. FX2-TH is operational on IBM system 360 or 370 computers and on the CDC 7600.
Date:
October 1978
Creator:
Shober, R. A.; Daly, T. A. & Ferguson, D. R.
Object Type:
Report
System:
The UNT Digital Library
COMMIX-1AR/P. a Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems, Volume 3: Programmer's Guide
The COMMIX-LAR/P computer program is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-lA to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a keg model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the program to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The internal aspects of the COMMIX-LAR/P program are presented, covering descriptions of subprograms, variables, and files. This document provides a description of each subroutine and variable, showing linkage among these and their relation to the equations and variables presented in Volume 1.
Date:
September 1992
Creator:
Garner, P. L.; Blomquist, R. N. & Gelbard, Ely M.
Object Type:
Report
System:
The UNT Digital Library
DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems
The mathematical development and numerical solution of the finite-difference equations are summarized. The report provides a guide for user application and details the programming structure of DIF3D. Guidelines are included for implementing the DIF3D export package on several large scale computers. Optimized iteration methods for the solution of large-scale fast-reactor finite-difference diffusion theory calculations are presented, along with their theoretical basis. The computational and data management considerations that went into their formulation are discussed. The methods utilized include a variant of the Chebyshev acceleration technique applied to the outer fission source iterations and an optimized block successive over-relaxation method for the within-group iterations. A nodal solution option intended for analysis of LMFBR designs in two- and three-dimensional hexagonal geometries is incorporated in the DIF3D package and is documented in a companion report, ANL-83-1.
Date:
April 1984
Creator:
Derstine, K. L.
Object Type:
Report
System:
The UNT Digital Library
Collected Reports on Fission Cross Sections of U237 in Thermal Neutron, Intermediate Neutron, and Degraded Fission Neutron Spectra
Part 1. The neutron fission cross section of U237 has been measured in a thermal neutron spectrum and in a somewhat degraded fission spectrum. The fission cross section for thermal neutrons is found to be <2 barns; the ratio of the fission cross section of U237 to that of U235 in the degraded fission spectrum is found to be 0.476 +- 15% which corresponds to [formula] in this spectrum equal to 0.66 +- 0.10 barns. Part 2. The average neutron fission cross section of U237 has been measured in a neutron energy range extending from approximately 100 ev to fission spectrum. the average fission cross section in this spectrum is found to be 0.70 +- 0.07 barns. Part 3. The low thermal fission cross section for U237 (<2 barns) indicated that the excitation function for fission probably shows an effective threshold. If the excitation function is like all other heavy element (Z > 90) neutron fission excitation functions, it will exhibit a region of approximate constancy starting at a neutron energy of 0.5 to 1 Mev above its effective threshold and extending to a neutron energy in the neighborhood of 5.5 Mev. A hypothetical excitation function for neutron fission of …
Date:
January 1, 1955
Creator:
Cowan, G. A. (George A.), 1920-2012
Object Type:
Report
System:
The UNT Digital Library
Simplified Linear Equation Solvers : Users Manual
The solution of large sparse systems of linear equations is at the heart of many algorithms in scientific computing. The SLES package is a set of easy-to-use yet powerful and extensible routines for solving large sparse linear systems. The design of the package allows new techniques to be used in existing applications without any source code changes in the applications.
Date:
February 1993
Creator:
Gropp, William & Smith, Barry
Object Type:
Report
System:
The UNT Digital Library
Progress Report for August, 1955
This report of the Battelle Memorial Institute covers information on development regarding various materials.
Date:
September 1, 1955
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During April, 1956
A report about elevated-temperature properties of dilute uranium-aluminum and uranium-zirconium alloys. Hot-hardness measurements show that small amounts of wither aluminum or zirconium increase the hardness of uranium at elevated temperatures.
Date:
May 1, 1956
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During January, 1956
A report which discusses the response of dilute uranium alloys to heat treatment with the ultimate objective of developing high-strength fuel elements.
Date:
February 1, 1956
Creator:
Dayton, Russell W. & Tipton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Progress Relating to Civilian Applications During March, 1956
A report about elevated-temperature tensile properties of dilute uranium alloys. Alloys up to 2 a/o aluminum and 4 a/o zirconium have been fabricated to rod and are being tested at temperatures up to 500 C.
Date:
April 2, 1956
Creator:
Dayton, Russell W. & Tripton, Clyde R., Jr.
Object Type:
Report
System:
The UNT Digital Library