Serial/Series Title

211 Matching Results

Results open in a new window/tab.

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2 (open access)

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Object Type: Report
System: The UNT Digital Library
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1 (open access)

The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).
Date: October 1964
Creator: Helm, J. W.
Object Type: Report
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Object Type: Report
System: The UNT Digital Library
Hanford Controlled Potential Coulometer (open access)

Hanford Controlled Potential Coulometer

Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
Object Type: Report
System: The UNT Digital Library
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation (open access)

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Date: January 1964
Creator: Hanford Atomic Products Operation. N-Reactor Project Section.
Object Type: Report
System: The UNT Digital Library
Hanford Radiological Sciences Research and Development Annual Report for 1963 (open access)

Hanford Radiological Sciences Research and Development Annual Report for 1963

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date: January 1964
Creator: Gamertsfelder, C. C. & Green, J. K.
Object Type: Report
System: The UNT Digital Library
Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory (open access)

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965

Report documenting radioactive fallout across the world, including material in the atmosphere, on land, and that has deposited into food and water supplies.
Date: October 1, 1965
Creator: Hardy, Edward P., Jr. & Rivera, Joseph
Object Type: Report
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
Object Type: Report
System: The UNT Digital Library
Health Physics Instrument Manual (open access)

Health Physics Instrument Manual

Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date: May 16, 1963
Creator: Davis, D. M. & Gupton, E. D.
Object Type: Report
System: The UNT Digital Library
Health Physics Research Reactor Hazards Summary (open access)

Health Physics Research Reactor Hazards Summary

Report describing the design and operation of the Health Physics Research Reactor, its core, and its support structures.
Date: 1962
Creator: Lundin, M. I.
Object Type: Report
System: The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility (open access)

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date: June 1961
Creator: Muraoka, J.
Object Type: Report
System: The UNT Digital Library
High-Density Concrete for Gamma and Neutron Attenuation (open access)

High-Density Concrete for Gamma and Neutron Attenuation

Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
Object Type: Report
System: The UNT Digital Library
The High Flux Isotope Reactor: Volume 1, A Functional Description (open access)

The High Flux Isotope Reactor: Volume 1, A Functional Description

Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.
Date: May 1964
Creator: Binford, F. T. & Cramer, E. N.
Object Type: Report
System: The UNT Digital Library
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings (open access)

The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
Object Type: Report
System: The UNT Digital Library
High Temperature Short-Time, Uranium Carbide-Metal Reactions (open access)

High Temperature Short-Time, Uranium Carbide-Metal Reactions

Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Date: March 1963
Creator: Christensen, J. A.
Object Type: Report
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
Object Type: Report
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: May-July 1960 (open access)

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
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C (open access)

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Object Type: Report
System: The UNT Digital Library
In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C (open access)

In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date: May 5, 1962
Creator: Jenks, G. H.
Object Type: Report
System: The UNT Digital Library
In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature : Design and In-Pile Operation of Loop L-2-27S (open access)

In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature : Design and In-Pile Operation of Loop L-2-27S

Report describing the design and operation of Loop L-2-275, which was used in the irradiation an aqueous thoria-urania slurry.
Date: 1962
Creator: Savage, H. C.; Compere, E. L.; Baker, J. M.; DeCarlo, V. A. & Shor, A. J.
Object Type: Report
System: The UNT Digital Library
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C (open access)

In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Object Type: Report
System: The UNT Digital Library
In-Pile Test of Prototype ML-1 Fuel Elements (open access)

In-Pile Test of Prototype ML-1 Fuel Elements

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
Object Type: Report
System: The UNT Digital Library
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962 (open access)

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Date: August 1962
Creator: Doman, D. R. & Pankaskie, P. J.
Object Type: Report
System: The UNT Digital Library