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Evaluation and Consolidation of Electrolytic Thorium
Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date:
June 15, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date:
March 15, 1957
Creator:
Trilling, C. A.
System:
The UNT Digital Library
Reactor Safety Quarterly Progress Report: May-July 1956
From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date:
March 15, 1957
Creator:
Miller, N. C.
System:
The UNT Digital Library
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956
From abstract: The vapor pressure determination of solid ThF4 has been completed. Experiments to determine the heat of formation of ThF4 by studying the reaction of ThF4 with SiO2 are described.
Date:
July 15, 1957
Creator:
Yosim, S. J. & Milne, T. A.
System:
The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits
Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date:
September 15, 1957
Creator:
Jones, L. H.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: August-October 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date:
November 15, 1957
Creator:
Trilling, C. A.
System:
The UNT Digital Library
Reactor Physics Primer
Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date:
November 15, 1957
Creator:
Lockwood, E. H.
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1957-January 1958
Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date:
February 15, 1958
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Neutron Physics Division Annual Progress Report, September 1, 1958
Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.
Date:
February 15, 1958
Creator:
Oak Ridge National Laboratory. Neutron Physics Division.
System:
The UNT Digital Library
Maintenance of ETR Coolant
Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
Date:
August 15, 1958
Creator:
Haas, F. C.
System:
The UNT Digital Library
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).
Date:
October 15, 1958
Creator:
Gilroy, H. M. & Edwards, R. J.
System:
The UNT Digital Library
Standard Practices Guide for Writing Experimental Operating Manuals
This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
Date:
December 15, 1958
Creator:
Ford, J. D.
System:
The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location
Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date:
January 15, 1959
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
Ionium Recovery Plant Design Report: Topical Report
This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date:
April 15, 1959
Creator:
Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
System:
The UNT Digital Library
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.
Date:
September 15, 1959
Creator:
Howell, J. D.
System:
The UNT Digital Library
Carbide Fuel Development: Phase 1 Report, Period of May 15 to September 15, 1959
From foreword: This report describes the work accomplished including the Conceptual Design task and the initial results of the tasks on Facility Design and Fabrication, Fuel Fabrication and Evaluation, and Fuel Reprocessing.
Date:
October 15, 1959
Creator:
Bolomey, R.; Lazerus, S.; Sapir, J.; Sofer, G.; Steinmetz, H.; Strasser, A. et al.
System:
The UNT Digital Library
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).
Date:
November 15, 1959
Creator:
Alm, G. V.; Binstock, M. H. & Garrett, E. E.
System:
The UNT Digital Library
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).
Date:
November 15, 1959
Creator:
Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
System:
The UNT Digital Library
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.
Date:
December 15, 1959
Creator:
Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
System:
The UNT Digital Library
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.
Date:
December 15, 1959
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Design Study: Sodium Modular Reactor
This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date:
January 15, 1960
Creator:
General Electric Company
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
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
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.
Date:
March 15, 1960
Creator:
Wilkinson, L. E.
System:
The UNT Digital Library