UNT Libraries Government Documents Department - 83 Matching Results

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Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies
Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Plutonium Recycle Critical Facility: Final Safeguards Analysis
Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
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.
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
The Thermal Hydraulics Laboratory at Hanford
Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
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.
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.
Thermal Conductivity of UO2
Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
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.
A Device for Recording Fuel Element Dimension on Punched Paper Tape
Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)
Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)
Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
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.
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis
This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
A New Model Concept for Large Nuclear Reactors
Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
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.
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).
Ultrasonic Resin Level Detector
This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels
Report that "describes the equipment, technologies of use, and reliability of an ultrasonic tester - designated UT-4 - capable of detecting very small defects in the brazed closures of reactor fuel elements" (p. 2).
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Prototype Burst Test Unit for irradiated Pressure Tubes
Report that "describes the development of a prototype test chamber in which sections of irradiated pressure tubes from the Hanford [Laboratories] reactors are burst at elevated temperatures" (p. 2).
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey
Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements
This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule
Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Critical Mass Studies of Plutonium Solutions
Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Irradiation Behavior of High Purity Uranium
Report that "describes the behavior of small, high purity uranium specimens irradiated under controlled conditions" (p. 2).
Welding Plutonium-Containing Fuel Elements
Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)
Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1
Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Magnetic Force Welding Sintered Aluminum Powder Materials
Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
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.
Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program
The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.
Beta-Gamma Dose Rates from U232 in U233
This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 3, July 1963 - November 1963
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.