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Applied Potential Corrosion of Aluminum : Final Report

Description: Report describing data resulting from dynamic tests to determine applied potential corrosion of aluminum.
Date: December 5, 1955
Creator: Sanborn, Kenneth L.
Partner: UNT Libraries Government Documents Department
open access

Remotely Operated Irradiation Facility : (Sample Carrier)

Description: Report discussing a possible solution for providing a remotely operated way of handling samples at an irradiation facility. Explanation of operating requirements, equipment, and a possible layout is included.
Date: December 8, 1955
Creator: Fox, J. C.
Partner: UNT Libraries Government Documents Department
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Test of Water Quality Velocity on Pitting of 72-S Aluminum

Description: Report discussing a test aimed at determining if high velocity water could cause severe pitting in 72-S aluminum. This test was designed after an increase in the amount of pitting-caused water leaks in reactors.
Date: December 8, 1955
Creator: Houck, William C.
Partner: UNT Libraries Government Documents Department
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Analytical applications of refractive index

Description: Report detailing the refractive index of solutions of uranyl nitrate, nitric acid and aluminum nitrate. This report builds upon preliminary data and a brief discussion that from a previous report. This report covers more accurate and detailed data that had be accumulated following the initial report.
Date: January 9, 1955
Creator: Burger, L. L.
Partner: UNT Libraries Government Documents Department
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Concrete Cone Anchor Tests

Description: This study was initiated to determine the minimum safety requirements for safe anchorage of electric pole lines. The objectives were to investigate the suitability of manufactured concrete pole line anchors for use at the Hanford Atomic Products Operation, to design a concrete anchor slug of optimum shape and size for manufacture, to determine by field tests the resistance pullout of the concrete anchor when buried at various depths under the most favorable condition, and to develop a safe desi… more
Date: March 18, 1955
Creator: Buchols, C. S.
Partner: UNT Libraries Government Documents Department
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Grain Refinement Produced by an Alpha Phase Anneal of Beta Phase Heat Treated and Water Quenched Uranium

Description: During an experiment involving alpha phase annealing (at 610 to 655 deg C for 5 and 10 min) of beta-quenched uranium, it was determined that the relatively coarse, irregular shaped grains (0.08 to 0.150 mm in diameter) in the beta-quenched structure, were replaced by fine equiaxed grains (0.04 to 0.09 mm in diameter).
Date: January 3, 1955
Creator: Gradner, H.R.
Partner: UNT Libraries Government Documents Department
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The Alpha Half-Life of the Isotope Pu-241

Description: A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.
Date: February 15, 1955
Creator: Gift, M. W.
Partner: UNT Libraries Government Documents Department
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Continuous Denitration Status of Development, January 12, 1955

Description: Experimental studies on continuous denitration performed in 321 Building resulted in the development of an agitated-through-type calciner. The performance of a paddle-agitated 4-in.-diameter by 44-in.-long reactor was sufficiently promising to warrant construction of a 16-in.-diameter by 8 ft.-long semi-plant scale model. This progress report summarizes the results of studies to date employing the semi-plant scale calciner.
Date: January 14, 1955
Creator: Szulinski, M. J.
Partner: UNT Libraries Government Documents Department
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Chemical Stability of Purex and Uranium Recovery Process Solvent

Description: The desirability of operating many of the Purex columns at elevated temperatures, ca. 50-70 C, has made it necessary to obtain data on the stability of the solvent at these higher temperatures. Since the present diluent, Shell Spray Base, will not be entirely safe at the upper temperature limit, a number of diluents with higher flash point have been investigated concurrently with Shell Spray Base. This report presents data covering the first phases of this investigation, namely, the effect of n… more
Date: March 2, 1955
Creator: Moore, R. H.
Partner: UNT Libraries Government Documents Department
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Interim Report: Investigation of Ultrasonic Decontamination

Description: The purpose of this investigation is to make a preliminary study and evaluation of the application of ultrasonic equipment and associated handling equipment to the problem of decontaminating reactor tube dummy pieces. Reactor Section is currently planning the construction of batch process nitric acid facilities for dummy decontamination. It was felt that use of ultrasonics together with a solution less corrosive than nitric acid might provide adequate decontamination at lower project cost than … more
Date: January 28, 1955
Creator: Reed, E. L.
Partner: UNT Libraries Government Documents Department
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Mechanical and Physical Properties of Uranium: Chapter 8 of Nuclear Metallurgy Lectures

Description: A knowledge of the mechanical and physical properties of uranium is important in understanding and explaining its pile behavior. The effects of irradiation on the properties of uranium will be dealt with in another chapter. However, it is important to know and understand the pre-irradiation properties of uranium prior to investigating the effects of irradiation.
Date: May 10, 1955
Creator: Rueschen, R. E.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Buried Waste Line Design Practice Interim Report No. 2: Underground Pipeline and Structure Corrosion Study Program

Description: This report has been prepared to review the status of design for buried waste line and presents the major factors involved in support of the conclusions. This report is the second in a series reporting on the general subject of underground corrosion. The first on cathodic protection of waste lines noted the technology of stainless steel and its effect on existing waste line and recommended continued use of the cathodic protection. Experience with buried stainless pipe had shown that, unless pro… more
Date: April 1, 1955
Creator: Jaske, R. T.
Partner: UNT Libraries Government Documents Department
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Examination of Irradiated Uranium-Chromium Alloy Slugs

Description: Production Test 313-105-13-M authorized the irradiation of a uranium - 0.4 atomic per cent chromium alloy to determine the relative stability of this material during irradiation. Five tubes, each containing six four-inch alloy slugs, were irradiated to exposures ranging from 156 to 834 MWD/T. This report describes the results of the visual examination of the bare uranium alloy slugs and the results of the test to determine slug breaking strength. The breaking strength of both the U-Cr alloy slu… more
Date: February 14, 1955
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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The Occlusion of Hydrogen by Uranium During Several Types of Beta Heat Treatments

Description: As part of the recent intensified study of variables involved in the beta heat treatment of production uranium, the writer undertook a qualitative examination of the effects of heating and quenching media on the hydrogen content of pieces heat treated in slug form. Because of the limited amount of time available the work was necessarily restricted in scope. For the same reason no detailed study of any single heat treatment was attempted: rather, a number of beta treating schedules were selected… more
Date: March 3, 1955
Creator: Ray, William E.
Partner: UNT Libraries Government Documents Department
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Feasibility Report 100-DR WAPD Test Loop

Description: The purpose of this report is to present a HAPO proposal for the design and construction of a high-temperature, high-pressure light water recirculation test facility for the Westinghouse Electric Corporation, Atomic Power Division This report does not attempt to justify the feasibility of site location nor does it attempt to elaborate on such technical considerations as permissible test specimen heat generation and enrichment requirements which have been covered in an earlier document. Instead,… more
Date: March 15, 1955
Creator: Engineering Department, Hanford Atomic Products Operation, General Electric Company
Partner: UNT Libraries Government Documents Department
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Proposed Revision in Computations of MPC's for Long-Lived Radioisotopes

Description: Equations are developed for the computation of MPC's for radioisotopes assuming the excretion or retention to follow a power law rather than an exponential law. Computations are made for four isotopes on which some human data are available. Uncertainties in the initial data due to the use of intravenous injection to obtain the primary data, the definition of retention and the effects of age and diet are discussed.
Date: March 1, 1955
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
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Proposed Clean-Up System for Carbon Steel High Temperature Recirculation System

Description: It is the purpose of this document to outline a proposed addition to the previously considered clean-up systems as a possible solution for the maintenance of high purity water. A cyclone separator system has been devised in conjunction with the water clean-up of a high temperature recirculating reactor cooling system. By utilizing such a cyclone separator system, a high quality water can be obtained in a primary coolant system made up of carbon steel components without excessive clean-up costs.
Date: March 17, 1955
Creator: Pearl, W. L.
Partner: UNT Libraries Government Documents Department
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Stability of Chromel-Alumel Thermocouples in Carbon Dioxide at 1000°C

Description: Tests on twenty identically prepared 26 gauge Chromel-Alumel thermocouples have been completed. It appears that wires of this material without protection are unsatisfactory mechanically and thermoelectrically for service in atmospheres of CO₂ at 1000°C.
Date: November 29, 1955
Creator: Burton, H. H.
Partner: UNT Libraries Government Documents Department
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Summary of HAPO Research and Development Program on Ceramic Fuel Materials

Description: The Metallurgy Research Sub-Section at HAPO has conducted a research and development study of a variety of nuclear fuel materials. A summary of the status of the program currently being conducted on ceramic fuel material and a brief discussion of the future program is outlined below.
Date: December 12, 1955
Creator: Sanderson, M. J.
Partner: UNT Libraries Government Documents Department
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Initial Operating Procedures for 105-C Metal Examination Facility

Description: These initial operating procedures have been prepared for interim use during the first operation of Basins I, II, and III. They will be revised and included in the operating manual for the entire 105-C Metal Examination Facility.
Date: December 20, 1955
Creator: Reynolds, R. L.
Partner: UNT Libraries Government Documents Department
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Transient Flow of Steam-Water Mixtures

Description: In the analysis of problems involving transient flow and heat transfer in steam-water mixtures, it is necessary to derive an approximate integral equation of motion for a non-ideal compressible fluid in a duct having finite discontinuities in flow geometry. This equation is derived in this document.
Date: December 12, 1955
Creator: Tippets, F. E.
Partner: UNT Libraries Government Documents Department
open access

Safety Aspects of Purex Plant Concentrator Operation

Description: A study was made to evaluate the possibility of an explosive reaction occurring in the Hanford Purex Plant concentrators as presently instrumented. Results revealed that the occurrence of an explosive reaction in the Purex Plant concentrators with present instrumentation is very unlikely.
Date: December 23, 1955
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Comparison of Flame Photometer and Conductivity Meter for the Determination of NaCl from Respirator Testing

Description: periodically the Industrial Hygiene Unit has the occasion to perform efficiency tests on respiratory protective devices and on filter cartridges used with these units. A study of the relative merits of the flame photometer and conductivity meter was made to determine which is more applicable for the determination of NaCl in filter samples.
Date: September 26, 1955
Creator: Baum, J. W. & Gill, W. E.
Partner: UNT Libraries Government Documents Department
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