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10 M.C. Wide Band Amplefier and Scope
Technical drawing of an amplifier for a nuclear reactor.
10 MWe Sodium Deuterium Reactor Design Report
From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor.
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.
15 Mile Road/Edison Corridor Sewer Tunnel Failure Study, Detroit Area, Michigan
Partial abstract: "The study consisted of field and laboratory investigations, construction evaluation, and geotechnical and structural analyses to determine the cause(s) of distress and failure of a 2600-ft section of 12-ft 9-in. diameter concrete-lined sanitary sewer tunnel in the Detroit, Mich., area. [...] The report includes summaries of all pertinent construction records, results of all pertinent past and current field and laboratory tests on construction and geotechnical materials, and detailed geotechnical and structural analyses based on observed conditions and measured parameters."
15 MW Gas-Cooled Closed-Cycle Reactor Power System Study: Final Report, Volumes 1-2
This report covers a feasibility study for a 15 megawatt gas cooled reactor power system, conducted by the Ford Instrument Company Division of the Sperry Rand Corporation during the months of March to August 1956.
20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission
Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
20-ton and 1/2-ton High Explosive Cratering Experiments in Basalt Rock: Final Report, August 1962
This report describes the Sandia Corporation participation and results related to Project Buckboard: the detonation of three 40,000-pound and ten 1000-pound high-explosive charges in basalt rock to establish depth -of-burst curves.
20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962
From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
"25" Critically Consultation with J. W. Morfitt : April 3, 1950
Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
Final design for the 30 megawatt intermediate heat exchanger and steam generator.
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis
Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
30 Rv. Power Supply
Technical drawing of electronic circuits and power supplies to nuclear reactors.
A 37,500 KW Power Reactor with Competitive Possibilities
The following report follows the study on economics of nuclear power generation using a light water reactor.
80" Bubble Chamber Expansion System Preliminary Operating Procedures
These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of making it easier to adapt certain expansion system procedures to programmed control by a process control computer.
80" Bubble Chamber Expansion System Summary of Piston Motion Studies
Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.
80" Chamber - Low Energy Beams
One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.
#85-Classical Model of a Light Source
Using classical concepts, the author establishes a model of a luminescence atom or molecule.
100-N Decontamination Facility Design Guide.
Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
100-Ton Test at Trinity: Report on Earth Velocity Measurements
Apparatus, field layout, miscellaneous testing, and the method of analysis of a 100-ton test at Trinity.
100-Ton Test : Measurement of the Velocity of Sound
Abstract: The velocity of sound at the time of 100-ton shot at Trinity was measured to be 1116.1 ft/sec. Values of blast pressure computed from the excess velocity are given, but are not considered as reliable.
200-Mwe Prototype Large SGR: Reactor Structure Design and Evaluation
From abstract: This document presents the reactor structure design and evaluation for a 200-Mwe prototype large SGR.
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
300-400 V Regulated Supply
1 technical drawing of a regulated supply of 300-400 volts for nuclear reactors.
The 300 H.P. Benz Aircraft Engine
This report provides a description of the Benz 300 H.P. aircraft engine containing 12 cylinders placed at a 60° angle. It includes a detailed description of the development of the constructional points, particularly the cylinders, pistons, and connecting rods, as well as the engine fitting, lubrication, oil pumps, bearings, oil tank, fuel pump, carburetors, and cooling system. There are seven pages of illustrative figures at the end of the report.
300-KV Pulser Transformer and Pulser.
Photographs and working drawings are presented for a small (approximately 4.25 X 7 X 9 inch) 300Kv pulse transformer having double-conical secondaries each with a corona ring at its greatest diameter. The pulser circuit is shown but no text is included.
300 Mc Transmitter Pulser
Technical drawing of pulse generators for use in nuclear reactors.
327 Basin Aluminum Corrosion Test
An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.
568 Report
Final report for a grant contract documenting information about the scope of the project and results.
709 Program for Reduction of Exponential Pile Data
A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
The 1000 HP Traffic Airplane of the Zeppelin Works in Staaken
Report details the characteristics and advantages of the swift traffic airplane constructed by Zeppelin Works at Staaken. The maximum speed, weight, construction, layout, and landing capabilities of the plane are included.
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1
From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description
From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept II System Description
From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program."
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description
From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description
From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual
Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
The 1350 F stress-rupture properties of two wrought alloys and three cast alloys
From Summary: "These properties compare favorably with those of the strongest similar alloys previously investigated. However, compared with a 60Cr-25Fe-15Mo alloy, the three cobalt-chronium-nickel cast alloys are inferior. A correlation of NACA and OSRD (Project NRC-8) data is presented, showing the variation of rupture strengths with temperature in the range of 1350^o to 2000^o for alloys."
1500 Uses Delay Unit
Technical drawing of signal generators in nuclear reactors.
A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations
An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method
An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
1706 KE Water Treatment for Out-of-Reactor Test Facilities.
Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
1706-KER Coolant Test Facility Operations Manual
This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
The 1926 German Seaplane Contest
The report discusses the problem of rating the various seaplane designs from the 1926 seaplane contest. The whole process of rating consists in measuring the climbing speed, flying weight and carrying capacity of a seaplane and then using these data as the basis of a construction problem.
The 1929 Rhon soaring-flight contest
The limitation of the 1929 contest to performance gliders necessitated the establishment of a formula which would make it possible to distinguish between performance gliders and school and training gliders. The sinking speed was therefore adopted as the basis for such a distinction, and the requirement was made that the sinking speed of a performance glider should not exceed 0.8 m/s. The rest of the report details the different entries with regard to design and performance.
The 1933 Contest for the Deutsch De La Meurthe Trophy
Report discussing the regulations and airplanes participating in the 1933 contest competing for the Deutsch de la Meurthe trophy.
The 1934 Contest for the Deutsch De La Meurthe Trophy
This report presents a description of the rules, history and new technical innovations in the Deutsch de la Meurthe Cup race of 1934.
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