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Chemical Research Section Progress Report for January 1950

Description: The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Partner: UNT Libraries Government Documents Department
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Polarographic Analysis of UNH in the IAW Stream

Description: The following report describes two rapid, micro methods for the determination of UNH in Redox waste samples that had been developed fir the concentration range 0.2 to 100 g/l.
Date: January 17, 1949
Creator: Alkire, G. J. & Carson, W. N.
Partner: UNT Libraries Government Documents Department
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Polarographic Determination of Hexone

Description: The following report describes polarographic methods that determine saturated aliphatic carbonyl compounds.
Date: November 10, 1949
Creator: Alkire, George J.
Partner: UNT Libraries Government Documents Department
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A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Description: Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Pap… more
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
Partner: UNT Libraries Government Documents Department
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Clarification of Redox Dissolver Solution by Centrifugation with Scavenger

Description: From statement of objectives: The purposes of the work described in this report are to provide data useful for designing and operating the dissolver solution clarification equipment to be installed in the Redox production plant.
Date: June 6, 1950
Creator: Allen, A. W.
Partner: UNT Libraries Government Documents Department
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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Partner: UNT Libraries Government Documents Department
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Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

Description: It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stabi… more
Date: December 23, 1959
Creator: Allen, C. W.
Partner: UNT Libraries Government Documents Department
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Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

Description: The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Physical Properties of Neutralized Zirflex Waste

Description: Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.
Date: June 8, 1959
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department Analytical Laboratory Manual

Description: The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.
Date: June 1959
Creator: Analytical Laboratory Manufacturing Operation
Partner: UNT Libraries Government Documents Department
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Partner: UNT Libraries Government Documents Department
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Development of Ribbed Jacket Tubing for PTRT

Description: One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel el… more
Date: September 4, 1959
Creator: Aungst, R. C.
Partner: UNT Libraries Government Documents Department
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Evaluation of Aluminum for use in Reactors Cooled by High-Temperature Recirculating Water

Description: aluminum has been considered as a material for cladding fuel elements to be used in reactors cooled by high-temperature recirculating water. Aluminum is abundant, chap, has a relatively low cross section for thermal neutrons, and is readily fabricated into complex shapes. For these reasons, it appears that the use of aluminum rather than steel, Zircaloy or other candidate materials for fuel element cladding, would result in considerable savings in operating expense. The actual economics will of… more
Date: April 5, 1960
Creator: Ayres, J. A.
Partner: UNT Libraries Government Documents Department
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100-N Decontamination Facility Design Guide.

Description: Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date: March 8, 1960
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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Suggested Major Equipment for NPR Water Quality Control Labs

Description: Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.
Date: July 30, 1959
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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Experimental Program for the PRTR Gas Loop

Description: Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical inter… more
Date: September 1, 1959
Creator: Baker, D. E.
Partner: UNT Libraries Government Documents Department
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Fast Neutron Sensitivity of the CP Meter

Description: Abstract: "The sensitivity to fast neutrons of a CP Meter ionization chamber of the type used for health physics beta and gamma survey measurements has been investigated."
Date: June 10, 1949
Creator: Baker, E. E.; Gydesen, F. R. & Whipple, G. H., Jr.
Partner: UNT Libraries Government Documents Department
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The Effect of the Speed of Emission on the Rise of a Plume of Stack Gases

Description: From introduction: "In this report an attempt was made to summarize the results of recent research on the effective height of smoke stacks. In this summary attention is paid only to the case in which the density of the stack effluent is the same as that of the surrounding air."
Date: November 20, 1950
Creator: Barad, M. L.
Partner: UNT Libraries Government Documents Department
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Thermal Hydraulic Bases for Selected PRTR Process Specifications

Description: This document presents the bases for those PRTR Process Specifications involving considerations of heat transfer and fluid flow. It will be noted that some of the bases incorporate information gained from laboratory experiments with electrically heated test sections simulating PRTR fuel elements. These experiments are described in some detail elsewhere.
Date: April 1, 1960
Creator: Batch, J. M. & Ambrose, T. W.
Partner: UNT Libraries Government Documents Department
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Photographic Observations of the Growth of Uranium Dioxide Crystals by Vapor Deposition

Description: Photographic observations of the behavior of uranium dioxide at high temperatures are of great value in designing and evaluating fuel elements. This paper reports the growth of uranium dioxide crystals by vapor deposition during out-of-reactor and in-reactor experiments.
Date: March 9, 1959
Creator: Bates, J. L. & Newkirk, H. W.
Partner: UNT Libraries Government Documents Department
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Effect of Irradiation Upon Mechanical Properties of Zircaloy-2

Description: It is well known that neutron damage generally causes increases in the yield and ultimate strength and a decrease in ductility of a metal. There is a continuing program at HAPO to determine the extent of these changes in Zircaloy-2 as functions of integrated neutron exposure, irradiation temperature, and reactor atmosphere. Three investigations from this program will be described and the results summarized. The first investigation deals with both annealed and cold worked Zircaloy-2 irradiated a… more
Date: September 4, 1959
Creator: Bement, A. L. & Gray, D. L.
Partner: UNT Libraries Government Documents Department
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Effects of Reactor Environment on Candidate PRTR Gas Loop Materials.

Description: The purpose of this program is to determine the effects of neutron radiation and reactor gaseous atmospheres on the structural integrity of candidate materials for the PRTR gas-cooled loop. An exploratory investigation is being conducted to select a high temperature resistant alloy for the fabrication of tubes and supporting appliances for the PRTR gas-cooled loop. In addition to a low neutron cross section, the material must be able to withstand the operating conditions outlined in Table 1.
Date: September 1, 1959
Creator: Bement, A. L.; Wheeler, K. R. & Pessl, M. J.
Partner: UNT Libraries Government Documents Department
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Diameter Measurements of Slugs Before and After Prolonged Heat Treatment

Description: Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."
Date: February 16, 1948
Creator: Bennett, Carl A. & Lane, J. J.
Partner: UNT Libraries Government Documents Department
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