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  Partner: UNT Libraries Government Documents Department
 Collection: Technical Report Archive and Image Library
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: July-September 1959
Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant. digital.library.unt.edu/ark:/67531/metadc304054/
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1959
Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant. digital.library.unt.edu/ark:/67531/metadc304053/
Gas-Cooled Marine Nuclear Power Plant: Interim Report. Project 16
From preface: The principal portion of this report is the scientific and engineering description of a novel reactor and power-plant scheme which was proposed by General Atomic in response to an invitation of the Maritime Administration. digital.library.unt.edu/ark:/67531/metadc304051/
Technical Foundations of TRIGA
From foreword: The TRIGA is a novel and unusually safe training, research, and isotope-production reactor that contains solid homogeneous uranium-zirconium-hydride-moderator fuel elements and operates at power levels in the range of from 10 kw to 250 kw. digital.library.unt.edu/ark:/67531/metadc304052/
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report. digital.library.unt.edu/ark:/67531/metadc860781/
Flux Control for Irradiation Experiments
Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control. digital.library.unt.edu/ark:/67531/metadc860812/
Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head
Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826. digital.library.unt.edu/ark:/67531/metadc860782/
Design Study Report for TARGET: A 1000-Mw(e) High-Temperature Gas-Cooled Reactor
Introduction: The scope of work for the contract stated that General Atomic was to undertake a preliminary design study and related exploratory development program for a 1000-Mw(e), advanced, gas-cooled reactor. digital.library.unt.edu/ark:/67531/metadc304064/
Development, Acceptance and Qualification Testing of the SNAP 10A Ejectable Heat Shield
From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report. digital.library.unt.edu/ark:/67531/metadc860806/
SRE Mark 2 Fuel Handling Machine
Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine. digital.library.unt.edu/ark:/67531/metadc860768/
Investigation of Turbocirculator for Target, a 1000-Mw(e) Reactor: Summary Report
The present study was undertaken for the purpose of determining the feasibility, establishing the required development program, and estimating the cost of a turbocirculator to provide the pumping power for a 1000-Mw(e) high-temperature gas-cooled reactor power plant as part of the TARGET program. This necessitated preliminary design of the turbocirculator in conjunction with the reactor power plant as well as the investigation of methods for the optimization of the turbocirculator and for its development. This study was carried out in sufficient detail to fix the methods required to resolve the problems that would be encountered during the course of a prototype program resulting in a turbocirculator for the TARGET power plant. digital.library.unt.edu/ark:/67531/metadc304065/
Tuna Longline Fishery and Fishing Grounds
From introduction: The Japanese tuna fishery, which formerly had for its fishing grounds almost the whole western Pacific and a part of the Indian Ocean, wherein its small vessels roamed at will, was reduced by the Pacific war to such a nearly complete state of destruction that little was left to remind one of its former condition. digital.library.unt.edu/ark:/67531/metadc304070/
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically. digital.library.unt.edu/ark:/67531/metadc860803/
Photovoltaic Advanced Systems Test Facility: Description and Operations Plan
From abstract: Photovoltaic modules and arrays are tested in the PASTF, along with power conditioning units and energy storage equipment related to photovoltaic systems. digital.library.unt.edu/ark:/67531/metadc304036/
Interpretation of Wireline Geophysical Logs : ERDA No.9 Stratigraphic Test Borehole DOE WIPP Site, Eddy County, New Mexico
From introduction: This report describes a stratigraphic core hole known as ERDA No. 9 drilled at the approximate center of the WIPP site. digital.library.unt.edu/ark:/67531/metadc304039/
Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations
Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations. digital.library.unt.edu/ark:/67531/metadc860770/
Power Cable Carrier Control (PC3) System
A control system has been developed that uses a carrier signal imposed on an existing ac power circuit to transmit commands. This system was specifically developed to control an entire solar collector field by sending sun-tracking information to the trough collectors or by commanding them to assume safe positions (STOW) if out-of-limit conditions were encountered. Objectives were to develop a control system that operates reliably and has enough functions to control an entire collector field, yet do it at less cost than for conventional approaches. Development, design, operating characteristics, and field testing and results of the new system, the Power Cable Carrier Control (PC³) System are described. digital.library.unt.edu/ark:/67531/metadc304041/
HNPF Control System Response During Transient Conditions
Abstract: This report documents the results of power ramps inposed on the HNPF during the month of January 1964. digital.library.unt.edu/ark:/67531/metadc860810/
Uranium Carbide Transient Heating Instruments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec. digital.library.unt.edu/ark:/67531/metadc860839/
Structural Test on the Final SNAP 10A Prototype System
Abstract: This report presents the results of the structural tests which were performed on the S10A-PSM-1A system to qualify the basic structural design for the anticipated launch environment. digital.library.unt.edu/ark:/67531/metadc860777/
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators. digital.library.unt.edu/ark:/67531/metadc860762/
Ignitron Resistance During High-Current Operation
Abstract: "A definition of average conduction resistance for an ignitron is established, and a test bank for determining the value of this resistance is described. Data are reported on four typical ignitron types for several currents in the kiloampere range. Oscillograms are presented to illustrate the change of current with time for a conducting ignitron in a ringing circuit." digital.library.unt.edu/ark:/67531/metadc304048/
Calandria Core Weld Joint Development
Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report. digital.library.unt.edu/ark:/67531/metadc860829/
Automatic Recording Unit
From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750. digital.library.unt.edu/ark:/67531/metadc304049/
A Study of the Error Involved in the Near Use of a Radio Interferometer
From abstract: This paper presents the results of a study of the error in radio interferometer measurements of near sources attributable to the use of asymptotic formulae, valid for distant targets. digital.library.unt.edu/ark:/67531/metadc304050/
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1960
Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant. digital.library.unt.edu/ark:/67531/metadc304057/
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP. digital.library.unt.edu/ark:/67531/metadc860779/
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: October-December 1959
Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant. digital.library.unt.edu/ark:/67531/metadc304055/
Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960
Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant. digital.library.unt.edu/ark:/67531/metadc304056/
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F. digital.library.unt.edu/ark:/67531/metadc860763/
UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements. digital.library.unt.edu/ark:/67531/metadc860771/
Feasibility Study of a 1000-Mwe Sodium-Cooled Fast Reactor: Volume 1 - Technical and Economic Potential
From abstract: The results of a feasibility study of a 1000-Mwe sodium-cooled fast-reactor are presented. digital.library.unt.edu/ark:/67531/metadc860809/
Use of Electricity in the Control of Sea Lampreys: Electromechanical Weirs and Traps and Electrical Barriers
From abstract: An account is given of experiments conducted in 1951 and 1952 with electro-mechanical and electrical barriers for the blocking and/or capture of sea lamprey runs in tributary streams of northern Lake Huron and northern Lake Michigan. digital.library.unt.edu/ark:/67531/metadc304071/
Directing the Movement of Fish with Electricity
From introduction: The Fish and Wildlife Service's Great Lakes Fishery Investigations has recently developed alternating current electrical devices which appear most promising as a means of controlling the parasitic sea lamprey in the Great Lakes. digital.library.unt.edu/ark:/67531/metadc304072/
Large SGR Control Rod Development
From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR. digital.library.unt.edu/ark:/67531/metadc860824/
Design, Construction, and Initial Operation of General Atomic In-Pile Loop
From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element. digital.library.unt.edu/ark:/67531/metadc304067/
The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide
From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux. digital.library.unt.edu/ark:/67531/metadc860778/
Reactor Technology Report Number 11: Physics
Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on physics information. digital.library.unt.edu/ark:/67531/metadc860833/
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer. digital.library.unt.edu/ark:/67531/metadc860817/
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors. digital.library.unt.edu/ark:/67531/metadc860828/
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors. digital.library.unt.edu/ark:/67531/metadc860811/
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices
Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator. digital.library.unt.edu/ark:/67531/metadc860818/
The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System
Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum. digital.library.unt.edu/ark:/67531/metadc860788/
The Design of a Side-by-Side Photovoltaic Thermal Systems for a Northeast All-Electric Residence
From background: The solar system design described in this report is for a residential two story house located in the Northeast region of the country typified by the Boston/Madison weather environment. A side-by-side photovoltaic/thermal system design was developed for the application. digital.library.unt.edu/ark:/67531/metadc304040/
General Instructions for Recovery of Radioactive Contaminated Equipment
Abstract: This document outlines the essentials of the planning and action necessary for the recovery of radioactive contaminated equipment following a radiological disaster. It lists the records which should be collected before a disaster and discusses the training of personnel for recovery teams. Radiation doses, radiation indicators, and protective clothing are all treated in a general fashion. Procedures are given for the actual recovery of equipment, with emphasis on personnel safety. Decontamination techniques and materials are then discussed. Graphs and simple calculations are presented for determining safe work limits and radiation doses under varied conditions. A list of typical sources for radiological supplies and a brief bibliography are also included. digital.library.unt.edu/ark:/67531/metadc860772/
An Approximate Solution for the Vaporization of Liquid Droplets Formed During Re-Entry Ablation
Introduction: The purpose of this report is to describe a mathematical model which will help solve the ultimate-particle-size problem by estimating the evaporative mass losses during that portion of re-entry when the fuel is in liquid form. digital.library.unt.edu/ark:/67531/metadc860773/
Photovoltaic Applications Definition and Photovoltaic System Definition Study in the Agricultural Sector: Volume 2, Technical Results
From introduction: The objectives of the technical effort are to identify and characterize agricultural energy demands that can effectively use P/V power systems and to determine performance and cost-estimates for the designs. digital.library.unt.edu/ark:/67531/metadc304033/
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I. digital.library.unt.edu/ark:/67531/metadc860792/
Photovoltaic Applications Definition and Photovoltaic System Definition Study in the Agricultural Sector: Volume 1, Executive Summary
From summary: The purpose of the study is to develop information that will contribute to the definition of the potential role of photovoltaics in meeting future energy demands in agriculture. digital.library.unt.edu/ark:/67531/metadc304032/
SNAP 2: Structural and Dynamic Analysis
Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented. digital.library.unt.edu/ark:/67531/metadc860813/
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