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Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 3: Long-Term Experiments at 1x10^4 Rad/Hour

Description: Report on experiments to assess the importance of radiation effects on waste glass corrosion. This third part contains a description of the experiments, results, and discussion, with conclusions and related appendices.
Date: February 1988
Creator: Abrajano, Teofilo Aniag; Bates, John K.; Gerding, Thomas J. & Ebert, William L.
Item Type: Report
Partner: UNT Libraries Government Documents Department

The reaction on a float bottom when making contact with water at high speeds

Description: Tests were conducted to investigate the possibility of a serious accident arising from unintentional contact with the water in substantially horizontal flight at high speed. Referring to vector diagrams on Figure 2, it will be seen that a very dangerous condition may arise if the float be allowed to come in contact with the water at high speeds as, for example, when flying at high speed just above the water. The initial diving moment due to suction and drag combined may be great enough to cause the seaplane to nose under before the pilot is able to control the motion. The same test data indicate clearly the existence of forces and moments tending to produce the phenomenon observed by Mr. Carroll (Technical Note No. 287) when the maneuver is carried out at lower speeds, as in a landing.
Date: May 1, 1928
Creator: Richardson, H C
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactivity Absorbed by Xenon-135 in the SRE

Description: Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date: January 28, 1960
Creator: Woodruff, R. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactivity and Power Shape Control : Theory and Numerical Applications

Description: An optimization method, based on linear programming, has been developed which determines the enrichment distribution in a multizone reactor such that the desired power distribution is achieved at BOL, as well as the poison distribution during reactor operation such that the reactor is kept critical and the desired power distribution is retained. For the numerical implementation of the method, the CYPRUS code has been written. Results of the application of the method are presented and input specifications for the use of the code are described.
Date: June 1976
Creator: Tzanos, Constantine P.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactivity in the South Spoils and Hillside Dump at the Midnite Mine

Description: The Midnite Mine is an inactive open-pit uranium mine located on the Spokane Indian Reservation in Washington State. Drill samples from two large waste rock dumps on the site, known as South Spoils and Hillside Dump, were collected with a Becker hammer drill and evaluated to determine potential of the rock to generate acid mine drainage (AMD). Waste rock at this mine contains both pyrite and uranium, and AMD effects are more complicated on this site than most in that uranium is soluble in both acidic and neutral aqueous solutions. Although AMD protocols identified 26% of the South Spoils samples as potentially acid, under 7% of the spoil samples were actually producing acid. Considerable calcite exists in the South Spoils, and weathering feldspars further contribute to acid neutralization. The Hillside Dump has low concentrations of pyrite and calcite that acid-base accounting protocols would predict to be non-acidic. Accumulation of sulfate in rocks with concentrations of less than 0.3% S causes some of those normally non-acid producing rocks to produce acid in the Hillside Dump.
Date: 1996
Creator: Moore, Bruce W.; Price, Jesse W. & Gardner, Ted
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactivity Studies During Drying and Relocation of Lead-Zinc-Gold Tailings: Phase 1 - Preliminary Evaluation and Laboratory Testing

Description: The U.S. Bureau of Reclamation requested U.S. Bureau of Mines (USBM) assistance in developing design data for moving lead-zinc-gold tailings from their current location without disrupting the existing chemically stable conditions. This report presents results of USBM work in determining (1) the minimum required time to air dry the tailings to approximately 20 pct moisture under various drying conditions both in the laboratory and in the field, (2) the degree of oxidation or reduction that occurs during drying, (3) the effect of lime or cement addition before drying, and (4) the likely equilibrium conditions of the dried tailings after deposition at the new location. The limited number of tests performed by the USBM in the available time frame established trends in oxidation levels but did not provide absolute statistical validity of data values. All data from drying and oxidation testing are included in appendices to this report.
Date: 1995
Creator: Froisland, L. J. & Lym, P. B.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: April 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: March 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: May 1966

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: November 1965

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: December 27, 1965
Creator: Adams, R. M. & Glassner, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: September 1966

Description: Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Engineering Division Quarterly Report, June 1, 1949 - August 31, 1949

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: October 7, 1949
Creator: Argonne National Laboratory. Reactor Engineering Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Flow Studies : Full Scale Model Flow Tests

Description: From foreword: This report contains the test results and analysis of test results of flow studies and reactor vessel internals. Tests were performed at, below, and above the PM-1 design flow rate to observe flow distribution and pressure drops within the reactor vessel, as well as the overall reactor vessel pressure drop.
Date: June 1961
Creator: Taylor, W. J.; Starr, I. & Baer, R. L.
Item Type: Report
Partner: UNT Libraries Government Documents Department

N-Reactor Operational Safety Review

Description: Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.
Date: August 19, 1963
Creator: Trumble, R. E.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Physics Primer

Description: Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date: November 15, 1957
Creator: Lockwood, E. H.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor

Description: Reactor physics studies in the Engineering Mockup Critical (EMC) assembly of the Fast Test Reactor (FTR) facility are reported. The study included measurements of the neutron spectrum, Doppler effect, sodium-void worth, reaction rates, subassembly worths, material replacement worths, and FTR control, safety and shim rod worths. Each of these physics studies were made in a clean plutonium (low-Pu-240) fuel composition environment and a dirty plutonium (high-Pu-240) fuel composition environment. The fuel studies were in support of determining the attendant effects of operation and safety of utilizing Light Water Reactor (LWR) plutonium fuel in the FTR. Comparison of the measured and calculated results are presented.
Date: July 1976
Creator: Pond, R. B.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Physics Studies in the GCFR Phase-II Critical Assembly

Description: The reactor physics studies performed in the gas cooled fast reactor (GCFR) mockup on ZPR-9 are covered. This critical assembly, designated Phase II in the GCFR program, had a single zone PuO₂-UO₂ core composition and UO₂ radial and axial blankets. The assembly was built both with and without radial and axial stainless steel reflectors. The program included the following measurements: small-sample reactivity worths of reactor constituent materials (including helium); ²³⁸U Doppler effect; uranium and plutonium reaction rate distributions; thorium, uranium, and plutonium alpha and reactor kinetics. Analysis of the measurements used ENDF/B-IV nuclear data; anisotropic diffusion coefficients were used to account for neutron streaming effects. Comparison of measurements and calculations to GCFR Phase I are also made.
Date: September 1976
Creator: Pond, Robert B.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Physics Studies in the GCFR Phase III Critical Assembly

Description: The third phase of the gas cooled fast reactor (GCFR) program, ZPR-9 Assembly 30, is based on a multi-zoned core of PuO2-UO2 with radial and axial blankets of uranium dioxide. Studies performed in this assembly will be compared to the previous phases of the GCFR program and will help to define parameters in this power-flattened demonstration plant-type core. Measurements in the Phase III program included small sample reactivity worths of various materials, central reaction rates and reaction rate distributions, absorption-to-fission ratios and the central point conversion ratio and the worth of steam entry into a small central zone. The reactivity change associated with the construction of a central pin zone in the core and axial blanket was measured. Reaction rate and steam entry measurements were repeated in the pin environment. Standard analysis methods using ENDF/B-IV data are described and the results are compared to measurements performed during the program.
Date: March 1980
Creator: Argonne National Laboratory. Applied Physics Division.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Reactor Physics Studies in the Steam Flooded GCFR-Phase 2 Critical Assembly

Description: A possible accident scenario in a Gas-Cooled Fast Reactor (GCFR) is the leakage of secondary steam into the core. Considerable analytical effort has gone into the study of the effects of such an accidental steam entry. The work described in this report represents the first full scale experimental study of the steam-entry phenomenon in GCFRs. The reference GCFR model used for the study was the benchmark GCFR Phase II assembly, and polyethylene foam was used to provide a very homogeneous steam simulation.
Date: August 1978
Creator: Bhattacharyya, S. K.
Item Type: Report
Partner: UNT Libraries Government Documents Department