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Materials for Fluorine Generator Anode Assemblies
Corrosion of anode assembly materials in fluorine generators is pronounced, therefore, selection of the proper materials for construction is important. Several metals and alloys have been tested for corrosion resistance when anodic in a fluorine test cell. In general, copper, copper alloys and magnesium alloys offer the best corrosion resistance.
Date:
September 28, 1956
Creator:
Simmons, R. E.; Rossmassler, W. R.; Hoskins, C. W. & Johnston, R. A.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
1959
Creator:
Leppard, J. A.
Object Type:
Report
System:
The UNT Digital Library
Fluidization in Tapered Beds
Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.
Date:
February 14, 1958
Creator:
Rossmassler, W. R. & Harris, R. L.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
May 27, 1959
Creator:
unknown
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Some Thermodynamic Properties of Freon-114
Introduction: The thermodynamic properties of Freon-114 presented herein supplement those of Volume I and encompass a range of temperature above the critical to 400 F &176 F.
Date:
September 3, 1959
Creator:
Van Wie, N. H. & Ebel, Robert A.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Irradiation Cycling on Pressurized Water Reactor Blanket Fuel Elements
From introduction: This report details the results of the post-irradiation examination of a test involving one defected rod and one undefected rod.
Date:
March 13, 1957
Creator:
Eichenberg, John D.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Reactor Technology Quarterly Report
Introduction: The experimental work reported here was undertaken as a part of the over-all design and development program for a nuclear reactor pressure vessel.
Date:
April 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
1957
Creator:
Wheelock, C. W.
Object Type:
Report
System:
The UNT Digital Library
SRE Fuel Element Damage: An Interim Report
Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date:
November 30, 1959
Creator:
Jarrett, A. A.
Object Type:
Report
System:
The UNT Digital Library
Transistorized Trip Circuit for Critical Assemblies
Abstract: A transistor trip circuit intended for critical assemblies and which provides maximum safety against human error or component failure is described.
Date:
February 24, 1958
Creator:
Wade, E. J. & Davidson, D. S.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
December 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956
From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date:
March 1, 1957
Creator:
North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Health Physics Report: October-December 1957
Summary: A survey was made of KAPL personnel currently exposed to radiation relating to their previous work with radiation or radioactive materials.
Date:
June 4, 1958
Creator:
unknown
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Process Engineering Report on Production of Thorium at Iowa State College
Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
Date:
January 16, 1952
Creator:
Bulkowski, H. H.; Holby, G. V.; Pfeiffer, C.; Maerker, J. B. & Winn, F. W.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
January 18, 1957
Creator:
Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Object Type:
Report
System:
The UNT Digital Library