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982
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923
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639
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156
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8
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6
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4
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2
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NACA Research Memorandums
335
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275
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140
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43
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37
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33
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27
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Macroscopic fission cross section ratio of Pu{sup 239} to U{sup 235} as a function of exposure for two lattices and two slug types
None
Date:
March 17, 1958
Creator:
Stanton, L. K.
System:
The UNT Digital Library
Analysis of distortion data from production test IP-68-A-90-FP: Comparison of void-free fuel elements with standard production fuel elements
None
Date:
November 21, 1958
Creator:
Stewart, K. B.
System:
The UNT Digital Library
Hanford Laboratories Operation monthly activities report, December 1957
This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for December 1957.
Date:
January 15, 1958
Creator:
unknown
System:
The UNT Digital Library
Operating conditions for Pt IP-205-A, irradiation of Zircaloy-2 jacketed rod-and-tube elements in the KER Loops
None
Date:
November 25, 1958
Creator:
Kratzer, W. K.
System:
The UNT Digital Library
Calculations of buildup of plutonium isotope and burnout of U{sup 235} in 1.44% U{sup 235} enriched uranium
In order to investigate the rupture stability of uranium elements irradiated at power generations per unit length larger than those encountered in natural uranium fuel elements, three partial columns of 1.44% U{sup 235} enriched, internally-externally cooled, uranium elements were irradiated in PT-IP-1-A. After discharge and examination of the fuel elements 25 pieces (182.5 pounds) of this metal were available for special analysis of U{sup 235} burnout and plutonium content. The average exposure of these pieces was 2,187 {+-} 6% MWD/Ton. The purpose of this document is to summarize some calculations of buildup of plutonium isotopes and burnout of U{sup 235} in an attempt to correlate calculations with the results from experimental analysis.
Date:
December 1, 1958
Creator:
Niemuth, W. E.
System:
The UNT Digital Library
Summary of information for U.K. -- Information request on gamma flux monitor
Summarized herein is the available information on the subject, ``Reactor Gamma Flux Monitors.`` Apparently, a misunderstanding exists between the U.K. representatives and the related information presented by Dr. Nilson at the Argonne meeting July 24 and 25th. Dr. Nilson`s reference at the US/UK meeting was to the use of gamma-compensated neutron detection chambers at Hanford. Such chambers have been designed and used in one old reactor for a short period as a prototype for a detector for the octant monitor system. No gamma compensated chambers are in any of the reactors at present. Under development is a neutron flux indicating system which will operate in the intermediate range (10{sup {minus}7} to 10{sup {minus}1} full power) and will use commercially available gamma compensated ion chambers. These will be used to provide signals for reactor period meters. At Hanford there has been no operating experience with gamma flux monitors as such or with extensive in core neutron flux monitors. Characteristics of systems under development are given for information as well as current information on the octant system.
Date:
December 4, 1958
Creator:
Nilson, R. & Dunbar, A. G.
System:
The UNT Digital Library
Comparison of the value of four ``corner`` rods the poison spline system for the ``K`` Reactors
The feasibility of adding four ``corner`` rods to the K Reactor`s 20-rod HCR system is being investigated. It is necessary to compare the costs and production gains of this method for gaining additional reactivity and heat distribution control with other supplementary control systems. This document presents the results of an investigation of the production gains that could be made by adding four rods to the KE Reactor HCR system.
Date:
October 27, 1958
Creator:
Franklin, F. C. & Wolf, W. H.
System:
The UNT Digital Library
Corrosion test of irradiated uranium in monoisopropylbiphenyl (RM-171)
The use of organic cooling media for nuclear reactors operating at high power levels predicates the use of a coolant which will not react violently with metallic uranium in the event of a fuel element failure. This report describes the testing, and subsequent examination, of two pieces of irradiated uranium which were immersed in monoisopropylbiphenyl (MIPB) at high temperatures and pressures for periods of time up to twenty-five days. The uranium samples had different irradiation histories and cooling times. Similar experiments had been performed with unirradiated uranium by the Corrosion and Coatings Operation, and it was wished to determine whether irradiated uranium would react with MIPB in a different manner.
Date:
November 11, 1958
Creator:
Brandt, R. L.
System:
The UNT Digital Library
Airborne Reconnaissance Project, Ruby Range and Sweetwater Basin, Montana
Abstract: A low-level airborne radioactivity survey of parts of Beaverhead and Madison Counties in southwestern Montana was undertaken from June 6 to October 14, 1955. Flying centered around the Ruby Range-Sweetwater Basin area and concentrated on the Precambrian metamorphic complex and Tertiary lake-bed sediments. No commercial uranium deposits were discovered, and no extensions were found of the few known small occurrences. Five areas of high background detected through the survey were investigated on the ground.
Date:
April 1958
Creator:
Pruitt, Robert G., Jr. & Magleby, Dan N.
System:
The UNT Digital Library
Minutes of the Fifth Trifolium Instrumentation Conference: Brookhaven National Laboratory, October 22-26, 1956
Introduction: These minutes report the fifth of a series of instrumentation conferences held on a classified basis with the atomic energy projects of Canada, the United Kingdom, and the United States participating.
Date:
February 1958
Creator:
unknown
System:
The UNT Digital Library
A Study of Fabricating Beryllia by Cold Compaction and Extrusion Techniques
From introduction: "This report presents the results of the preliminary studies of two fabrication methods aimed at producing high density beryllia shapes more economically. The method were cold compaction and sintering, and extrusion and sintering."
Date:
July 1958
Creator:
Harkulich, Theodore M. & Higbie, Kenneth B.
System:
The UNT Digital Library
Proceedings of the second symposium on the application of pulsed neutron source techniques : held at the Lawrence Radiation Laboratory, Berkeley, California, December 4 and 5, 1958
Report describing the proceedings of the second symposium on the application of pulsed neutron source techniques.
Date:
1958-12-04/1958-12-05
Creator:
unknown
System:
The UNT Digital Library
AEC Hot Cells and Related Facilities
Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Date:
May 1958
Creator:
Fosdick, Ellery R.
System:
The UNT Digital Library
Fringe isotope production
The purpose of this work has been to determine the production rate of tritium in fringe Li-Al alloy columns with the degree of precision necessary for economic analyses of such reactor loadings. These results are provided for use in such an analysis. This experiment indicates the production rate of tritium in the outermost fringe tubes to be T = 0.0216 M{sub E} = 0.175 M{sub t} where T = grams of tritium per full length (67 pieces) charge of Li-Al alloy material; M{sub E} = MWD/adjacent ton of E metal; M{sub t} = MWD/adjacent tube of E metal. The above values should apply for fringe loads utilizing greater or smaller quantities of E metal; that is, for isotope production loadings which are over or under-compensated from a reactivity standpoint. In the actual test load it was calculated that one gram of tritium and 13.5 grams of Pu were made for each 21.3 grams of U-235 burned up. During the same time interval the displaced uranium loading would have generated 24.3 grams of Pu and burned up 29.9 grams of U-235. The factor which seems to limit the accuracy with which these data can be interpreted is the ratio of the …
Date:
November 11, 1958
Creator:
Bunch, W. L.
System:
The UNT Digital Library
Purging of surface condenser tubes CA-719: Study report
This document provides the conclusions and recommendations of the study of purging of surface condenser tubes. (FI)
Date:
January 7, 1958
Creator:
Wood, V. W.
System:
The UNT Digital Library
Production Test IP-98-I revised tube charge pattern for graphite annealing: Interim Report
Graphite shrinkage of 0.60 inches (approximately 30 per cent) has been observed at F Reactor in the region of maximum graphite distortion. A reduction of graphite distortion at B Reactor of 0.60 inches in the top-center and 0.32 inches in the top-far region also has been observed. Analysis of the vertical traverse data indicates that continued graphite annealing with resultant decrease in graphite distortion might be anticipated although perhaps at a reduced rate. No significant detrimental effects have been observed from operation with either the increased charge length or the flux slightly skewed to the front of the reactor. Operation with severe flux skewing resulted in detrimental control effects. It is recommended that operation with the flux skewed to the front of B and F Reactors through the use of a longer charge (centered slightly upstream of the graphite century-line) be continued subject to periodic review.
Date:
December 18, 1958
Creator:
Graves, S. M.
System:
The UNT Digital Library
Possible explanation of 105-K graphite stack distortion
In the course of trying to predict the shape of NPR horizontal rod and process tube channels after several years of operation, data from 105-K were referred to. While looking at the 105-K data the following possible explanation of the ``K`` reactor distortion phenomenon occurred to me. It is written up in this document as a possible aid to those responsible for evaluating the stack distortion problem in the ``K`` reactors. Data and references to data are presented first and then an analysis of the data is presented. The author does not purport to be an expert on the ``K`` stack distortion or graphite technology but has written this analysis because it appears to be a plausible explanation of existing conditions.
Date:
October 23, 1958
Creator:
Haugland, G. T.
System:
The UNT Digital Library
I&E Depleted Uranium Fuel Element Ruptures Experienced Under PT-IP-132-AC
Beginning in February, 1958, a sufficient quantity of seven-inch dip canned I & E depleted uranium fuel elements was prepared for irradiation to produce eleven kilograms of plutonium, containing at least twenty per cent of the Pu-240 isotope, as authorized by the Atomic Energy Commission. Subsequently, eighty-four columns in C reactor were partially charged with the finished depleted fuel under PT-IP-132-AC. To date, ten depleted ruptures have been sustained, after being irradiated six to eight months toward a planned accoumulated goal exposure of 210 MWD per column or a total irradiation time approximating 12--14 months. The mechanism and cause of these failures is being thoroughly investigated. This document summarizes the fabrication history, irradiation experience to date, rupture examinations, and an investigation of process conditions which may have contributed to the high incidence of ruptures.
Date:
December 1, 1958
Creator:
Blanton, W. A.
System:
The UNT Digital Library
Hanford Laboratories Operation monthly activities report, October 1958
This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for October 1958.
Date:
November 15, 1958
Creator:
unknown
System:
The UNT Digital Library
Chemical Processing Department monthly report, July 1958
The July, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date:
August 22, 1958
Creator:
unknown
System:
The UNT Digital Library
Generalized river model tests with heated effluent at Bonneville Hydraulics Laboratory
The distribution of the heated effluents discharged by Hanford reactors to the Columbia River has been a matter of interest since the early design stage of the first reactors. The pattern of this distribution is a major factor in determining the extent to which a downstream reactor is affected by those upstream, as well as the localized effects on the ecology of the river. Pollutional characteristics of the effluents are three - heat load (or temperature increase), chemical contents and radioactivity. The latter has received the greatest attention in connection with potential personnel exposure and effects on river biota; it has been assumed however, and generally confirmed by sampling that the measure of distribution of any one of these characteristics in the saw an for the others. Observed distributions of radioactivity for various river and reactor flow rates are documented. Unfortunately, any extrapolation of those observed distributions to altered flow conditions of river regimes is of questionable validity. Mathematical models of the problem have been formulated but have been of little value due to the necessity of measuring certain parameters under the conditions for which a solution is desired. Even so, calculated distributions provide only general patterns and would not …
Date:
October 15, 1958
Creator:
Corley, J. P.
System:
The UNT Digital Library
Status report -- Fuel element machining
This report summarizes the design and development work completed since May, 1957; the current status of fuel element matching problems, and the plans for future modifications to improve machining techniques.
Date:
February 12, 1958
Creator:
Nickolaus, J. W.
System:
The UNT Digital Library
K-Reactor water plant analysis
The reliability of the K-Reactor water plants has been reviewed by Research and Engineering personnel; this study augments a brief analysis of the KW generator failures incident given in my letter of October 6, 1958. Our attention has been directed largely to ascertaining the requirements of the system, the consequences of possible component failures, giving general assessment of the primary features upon which reliability depends and identifying potential improvements which would increase reliability or moderate the consequences of a major failure. Our attention is restricted to failures which might occur as a result of equipment failure, operator error or certain natural causes such as earthquakes; we have not weighed special considerations brought on by enemy action such as sabotage, for example, in this evaluation. R. S. Bell is providing an analysis of the operating and maintenance aspects of K water plant reliability to complement this engineering study. It is concluded that the basic elements of the system lend themselves to reliable operation. The lines of defense appear adequate in depth, that is, a primary system operated with BPA power, an emergency ``backup`` system consisting of two essentially independent steam driven generators driving selected pumps, and a ``last ditch`` system providing …
Date:
December 22, 1958
Creator:
Dickeman, R. L.
System:
The UNT Digital Library
Standard laboratory hydraulic pressure drop characteristics of various solid and I&E fuel elements
The purpose of this report is to present a set of standard pressure-drop curves for various fuel elements in process tubes of Hanford reactors. The flow and pressures within a process tube assembly under normal conditions are dependent to a large extent on the magnitude of the pressure drop across the fuel elements. The knowledge of this pressure drop is important in determination of existing thermal conditions within the process tubes and in predicting conditions for new fuel element designs or changes in operating conditions. The pressure-flow relations for the different Hanford fuel element-process tube assemblies have all been determined at one time or another in the 189-D Hydraulics Laboratory but the data had never been collected into a single report. Such a report is presented now in the interest of establishing a set of ``standard curves`` as determined by laboratory investigations. It must be recognized that the pressure drops of fuel elements in actual process tubes in the reactors may be slightly different than those reported here. The data presented here were obtained in new process tubes while reactor process tubes are usually either corroded or filmed, depending on their past history.
Date:
January 20, 1958
Creator:
Waters, E. D. & Horn, G. R.
System:
The UNT Digital Library