Access
Serial/Series Title
States
Counties
91 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
91
next
Aircraft Reactor Test Removal and Disassembly
Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date:
1960?
Creator:
Abbatiello, A. A. & McQuilkin, F. R.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3
This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date:
June 14, 1960
Creator:
Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System:
The UNT Digital Library
Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Date:
1960
Creator:
Argonne National Laboratory. Idaho Division.
System:
The UNT Digital Library
Gas-Cooled Reactors in the USA: A Survey and Recommendation
Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Date:
November 1960
Creator:
Armstrong, R. H.
System:
The UNT Digital Library
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.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Performance of HNPF Prototype Free-Surface Sodium Pump
Abstract: A free-surface centrifugal pump, incorporating a hydraulic bearing running in sodium, was operated at the conditions required for service in the HNPF.
Date:
1960
Creator:
Atz, R. W.
System:
The UNT Digital Library
Heavy-Water-Moderated Power Reactors: a Status Report
From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date:
March 1960
Creator:
Babcock, Dale Friend
System:
The UNT Digital Library
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.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
System:
The UNT Digital Library
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Date:
June 2, 1960
Creator:
Batch, J. M. & Toyoda, K. G.
System:
The UNT Digital Library
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.
Date:
August 26, 1960
Creator:
Blaine, H. T.
System:
The UNT Digital Library
Transportability Studies : ML-1 Nuclear Power Plant
Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.
Date:
April 1960
Creator:
Blakley, J. W.; Alcorn, J. S.; Del Valle, L. G.; Healy, P. W.; Moran, D. H. & Scott, W. S.
System:
The UNT Digital Library
A Feasibility Study for the Use of an Extended Pm¹⁴⁷ Source for Analytical Fluorescence Spectroscopy: Final Report
From summary: The design of a spectrometer with the requisite improvement in crystals facilitates X-ray tube fluorescence.
Date:
October 31, 1960
Creator:
Brech, Frederick
System:
The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date:
July 1960
Creator:
Bullinger, C. F. & Harrer, J. M.
System:
The UNT Digital Library
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.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library
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.
Date:
May 1, 1960
Creator:
Corporales, G. W. & Benson, P. R.
System:
The UNT Digital Library
Particle Accelerator Division Summary Report: April Through September 1960
Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
Date:
1960
Creator:
Crewe, Albert V.; FitzPatrick, John P.; Foss, Martyn H. & Manson, David S.
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Induction Welding for Remote Maintenance -- Final Report
Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.
Date:
March 1960
Creator:
Dean, D. E.
System:
The UNT Digital Library
Safe Handling of Chlorine Trifluoride and the Chemistry of the Chlorine Oxides and Oxyfluorides
Abstract: A discussion of the potential hazards of chlorine trifluoride is presented and a series of safe handling procedures is recommended.
Date:
November 11, 1960
Creator:
Farrar, R. Lynn, Jr.
System:
The UNT Digital Library