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- Steady-State Tests of a Reactor Safety Device
- Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
- A Device for Continuous Detection of Hydrogen in Sodium
- Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
- Analog Models for HNPF Control and Protection Studies
- Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
- Thermodynamic Diagrams for Sodium
- From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.
- A Vapor Pressure Chart for Metals
- From conclusions: There is a close enough correlation for most metals to give the chart some utility in estimating vapor pressure of metals.
- A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor
- From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
- Neutron Leakage from the 30 Megawatt SGR-P4 Reactor
- Abstract: The fast and thermal neutron leakage from the 30 megawatt SGR-P4 reactor has been studied by three independent methods.
- Operations Handbook for the North American Aviation, Inc. Research Reactor, Model L-3
- Report describing reactor components, operational characteristics, and operating instructions for the Model L-3 research reactor.
- High Temperature Liquid Metal Circulating System
- Introduction: The purpose of this experiment was to demonstrate that a liquid metal heat transfer system could be built and operated at very high temperatures.
- SRE Instrumentation and Control
- Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
- Sodium Reactor Experiment Pump Development
- Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.
- An Evaluation of the Calder Hall Type of Nuclear Power Plant
- Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
- Reference Design for an OMR-Powered 38,000-DWT Tanker
- Abstract: This report presents a reference design of an organic moderated and cooled reactor for the propulsion of a 38,000-dwt tanker.
- A Further Evaluation of the Calder Hall Type of Nuclear Power Plant
- Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
- Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel
- Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
- Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields
- Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields.
- Evaluation of Irradiated OMRE Fuel Elements First Core Loading
- Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
- Remote Maintenance Techniques for the Processing Refabrication Experiment
- Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.
- OMR Control-Safety Rod Component Development Tests
- Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
- Reactivity Absorbed by Xenon-135 in the SRE
- Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
- Organic Moderated Reactor Experiment : Safeguards Summary
- Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
- The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
- Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.
- Preliminary Test of Natural-Circulation Double-Tube Steam Generator
- Abstract: Testing of the Natural Circulation Steam Generator has been conducted with the Sodium Reactor Experiment. A necessary modification of the original feed-water control system was utilized.
- Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
- Abstract: The design and application of two computers for the HNPF protective system is discussed.
- Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties
- Abstract: In the present study, the variation of moderator composition was postulated to be effected by the inclusion of varying amounts of beryllium oxide in the graphite of an SGR.
- Development of a Fuel Handling System for an Organic Moderated Reactor
- Abstract: This report describes the features of several systems which were rejected as inadequate, and the evaluation of a design leading to the construction of a prototype cask and its associated equipment.
- OMR Degasifier Loop Experiment
- Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
- OMRE Fuel Plate Surface Temperature Measurement
- Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
- P-V-T Relationships of BF₃ Gas
- Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
- Hot-Pressure Bonding of OMR Fuel Plates
- Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
- Plutonium: Enriched OMR Cores
- Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
- Maritime Organic Moderated and Cooled Reactor
- Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
- The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
- "An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
- Organic Reactor Waste Gas Analyzer
- The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
- Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor
- Abstract: A conceptual reference design of a 318 Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described.
- Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F
- Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
- Terminal Status Report for the Processing Refabrication Experiment
- Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
- Analysis of Stresses in Bellows
- Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
- Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
- Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
- Valve Stem Freeze Seal for High-Temperature Sodium
- Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
- Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator
- Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
- Piqua Prototype Handling System
- Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
- An Advanced Sodium-Graphite Reactor Nuclear Power Plant
- Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
- A Multichannel Digital Recording System
- Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
- Hazards Analysis of the Organic Moderated Reactor Experiment
- Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
- Thermal Cycling Tests of Porous Uranium
- Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
- OMRE Fuel Removal and Shipping Equipment
- Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
- Fabrication Modification Development for OMRE Third Core Loading
- Abstract: This report describes the fabrication of elements for the OMRE third core loading.
- OMR (Piqua) Unitized Control-Safety Rod Prototype Tests
- Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
- 11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description
- Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described.