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Annual Report of the Boy Scouts of America: 1942 (open access)

Annual Report of the Boy Scouts of America: 1942

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1942, activities, service reports, honors, finance, organizational leadership, and other information about scouting programs.
Date: March 25, 1943
Creator: Boy Scouts of America
Object Type: Report
System: The Portal to Texas History
Annual Report of the Boy Scouts of America: 1937 (open access)

Annual Report of the Boy Scouts of America: 1937

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1937, activities, service reports, finance, honors, organizational leadership, and other information about scouting programs.
Date: March 25, 1938
Creator: Boy Scouts of America
Object Type: Report
System: The Portal to Texas History

Hurricane Harvey Data Call: Data through September 30, 2018

Compiled slides documenting data submitted by insurance companies for claims related to damage from Hurricane Harvey (August 2017) as of September 2018. It includes descriptive explanations as well as graphical and tabular representations of data.
Date: April 25, 2019
Creator: Texas. Department of Insurance.
Object Type: Presentation
System: The Portal to Texas History
Curatorial Facility Certification Program: Benchmarking Excellence (open access)

Curatorial Facility Certification Program: Benchmarking Excellence

Document providing information for applicants who want to certify a facility in Texas to house and manage certain cultural resources, antiquities, etc.: "The purpose of this handbook is to guide the applicant curatorial facility through the entire [Curatorial Facility Certification Program] process, from Application through to Self Evaluation and Field Review" (p. 5).
Date: January 25, 2007
Creator: Texas Historical Commission
Object Type: Book
System: The Portal to Texas History
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962 (open access)

Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 1962

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.
Date: October 25, 1962
Creator: Howard, C. L.
Object Type: Report
System: The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961 (open access)

Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961

This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
Date: August 25, 1961
Creator: Danielson, D. W.
Object Type: Report
System: The UNT Digital Library
Swaging Over Unground Pellets (open access)

Swaging Over Unground Pellets

This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date: January 25, 1961
Creator: Brown, R. L.
Object Type: Report
System: The UNT Digital Library
N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report) (open access)

N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
Object Type: Report
System: The UNT Digital Library
Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System (open access)

Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
Object Type: Report
System: The UNT Digital Library
Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station (open access)

Amendment No. 2 To Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.
Date: August 25, 1958
Creator: Commonwealth Edison Company
Object Type: Report
System: The UNT Digital Library
The Determination of Fission Product Gamma Doses (open access)

The Determination of Fission Product Gamma Doses

In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.
Date: February 25, 1957
Creator: Ruehle, William G.
Object Type: Report
System: The UNT Digital Library
The Chemistry of Vanadium: A Summary of the Non-Project Literature Through November, 1952 (open access)

The Chemistry of Vanadium: A Summary of the Non-Project Literature Through November, 1952

The non-project literature concerning the chemistry of vanadium has been summarized through November, 1952. The report is presented in terms of izo- and heteropoly vanadates and cationic forms of pentavalent vanadium, complexes of di-, tri-, and pentavalent vanadium, and oxidation potentials of various vanadium systems. A bibliography of 93 references is included.
Date: June 25, 1954
Creator: Frank, Andrew J.
Object Type: Report
System: The UNT Digital Library
Texas Register, Volume 47, Number 12, Pages 1541-1650, March 25, 2022 (open access)

Texas Register, Volume 47, Number 12, Pages 1541-1650, March 25, 2022

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date: March 25, 2022
Creator: Texas. Secretary of State.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Texas Register, Volume 47, Number 8, Pages 821-1020, February 25, 2022 (open access)

Texas Register, Volume 47, Number 8, Pages 821-1020, February 25, 2022

A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date: February 25, 2022
Creator: Texas. Secretary of State.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid (open access)

A Combined Distillation-Electrochemical Method for Recovery of Hydrofluoric Acid

Electrodialysis in an ion-exchange membrane cell was shown to be technically feasible for the concentration of an azeotropic mixture of HF and water. A flowsheet is presented for recovery of anhydrous HF by distillation and electrodialysis of the azeotropic residue. In the electrodialysis step, 2.6 kwhr of energy per pound of anhydrous product was consumed, with electricity at 1¢ per kilowatt-hour, the total operating cost of the electrodialysis equipment alone, including amortization, would be 6¢ per pound of HF.
Date: May 25, 1956
Creator: Marinsky, J. A. & Giuffrida, A. J.
Object Type: Report
System: The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I. (open access)

Preliminary Results of APPR Critical Experiments, Part I.

This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date: November 25, 1955
Creator: Williams, D. V. P.
Object Type: Report
System: The UNT Digital Library
Pb-Sn Alloy Replacements for UO2 Density Standards (open access)

Pb-Sn Alloy Replacements for UO2 Density Standards

A correlation between the optical densities if the Pb-Sn alloy system and UO2 with respect to Co^60 gamma radiation has been determined. This enables one to fabricate density standards of whatever geometry may be desired for one in the gamma absorptiometer by simply casting a Pb-Sn alloy of the proper composition to correspond to the density required.
Date: April 25, 1960
Creator: Christensen, J. A.
Object Type: Report
System: The UNT Digital Library
Preliminary Report on pH Control by Ion Exchange in High pH Systems (open access)

Preliminary Report on pH Control by Ion Exchange in High pH Systems

The primary purpose of a cleanup system in a recirculating water loop is to maintain the best possible water quality conditions. This is normally accomplished by continuously purifying all or a portion of the coolant. A secondary objective of the cleanup system is to help maintain the system pH at a constant value. A system that will satisfactorily accomplish both of these objectives is at times difficult to obtain. Generally the pH control characteristics are sacrificed in favor of the more important cleanup requirements. A somewhat new approach to the problem pf cleanup system design appears to offer a solution to this problem for high pH systems.
Date: April 25, 1960
Creator: Demmitt, Thomas F.
Object Type: Report
System: The UNT Digital Library
Oxygen Removal with Hydrazine- Interim Report (open access)

Oxygen Removal with Hydrazine- Interim Report

During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that filtered water will be used for this purpose. Since filtered water contains substantial amounts of dissolved solids (approximately 100 parts per million), and since it is saturated with air, this type of operation will have to be investigated with regard to corrosion problems. A particularly serious problem will be present after the system has been decontaminated, since the high temperature oxide films will have been removed and the bars metal surfaces will be exposed to the coolant.
Date: January 25, 1960
Creator: Demmitt, Thomas F.
Object Type: Report
System: The UNT Digital Library
Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1. (open access)

Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.

The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (loop decontamination factors).
Date: November 25, 1959
Creator: Weed, R. D.
Object Type: Report
System: The UNT Digital Library
Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles (open access)

Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations would be helpful in the design and selection of equipment. Some progress has been made toward gaining a greater knowledge of the bundle characteristics under low temperature conditions. This report includes the development of relationship for the effect of temperature on pressure drop.
Date: January 25, 1960
Creator: Gartin, W. J.
Object Type: Report
System: The UNT Digital Library
Stored Energy in BNL Reactor Graphite (open access)

Stored Energy in BNL Reactor Graphite

Radiation damage to graphite has several consequences of practical importance. The growth of graphite under radiation (Wigner's disease) in production reactors has always been a serious concern. The thermal conductivity of graphite decreases greatly with time of irradiation and is important in long range studies of reactor temperature problems.
Date: February 25, 1953
Creator: Chernick, J.
Object Type: Report
System: The UNT Digital Library
Neutron Streaming Through Boundaries in a Mock-Up of the SIR Rotating Plug (open access)

Neutron Streaming Through Boundaries in a Mock-Up of the SIR Rotating Plug

This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank source strength and dimensions did not permit the tests to be extended to the full plug height. In view of the concern aroused by the ORNL tests and the absence of fundamental information on the transmission of neutrons through steel and the addition height (12') available here resulted in a request for BNL to construct and test a mock-up of a sector of the SIR top plug in accordance with KAPL specifications.
Date: March 25, 1953
Creator: Kouts, Herbert, J. C.; Pratt, William, W.; Schamberger, Robert, D.; Shore, Ferdinand, J.; Sleeper, Harvey, P., Jr. & Susskind, Herbert
Object Type: Report
System: The UNT Digital Library
A Test of the Refraction Seismic Method on the Hanford Project (open access)

A Test of the Refraction Seismic Method on the Hanford Project

Information was desired on applicability of seismic methods of geophysical exploration in helping to better define and refine hydrological and geological factors affecting ground disposal of liquid radioactive wastes. To date most of information on the area geology has been obtained from surface mapping and well drilling, although it has long been recognized that geophysical techniques may greatly assist in defining the geology of the region. Although direct measurements are generally preferred to indirect measurements have proven extremely valuable in many applications. Careful analysis of field data from geophysical measurements, and correlation with known geologic conditions, should provide significant knowledge of earth formations. Geophysical methods do not directly determine depth, type and composition of underground earth materials, but rely rather on detecting differences in physical properties (elastic wave velocity, magnetic susceptibility, density or electrical resistivity) of such earth materials.
Date: September 25, 1959
Creator: Raymond, J. R.
Object Type: Report
System: The UNT Digital Library