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Preparation and Physical Properties of Uranium Hydride

Description: Report discussing the preparation of uranium hydride and its properties such as density, crystal structure, and number of atoms per unit cell. From abstract: "The pressure-composition isotherm as well as other data indicates that uranium hydride is a true compound."
Date: 1948
Creator: Spedding, F. H.; Newton, A. S.; John, I. B.; Johnson, O.; Daane, A.; Nottorf, R. W. et al.
Partner: UNT Libraries Government Documents Department

Preparation and Properties of Refractory Sulfides

Description: From abstract: "The methods of preparation of the sulfides of cerium, thorium, uranium, and barium are discussed. Where necessary, the apparatus are described. Procedures for the handling and grinding of the sulfides and hydrides which are used for their preparation are given...The physical, mechanical, chemical, and thermodynamic properties are given for various sulfide refractories which have been developed at the Berkeley, California chemical laboratories."
Date: 1948
Creator: Brewer, Leo; Bromley, Leroy; Gilles, Paul. & Lofgren, Norman
Partner: UNT Libraries Government Documents Department

Review of the stack discharge active particle contamination problem

Description: Quantities of the order of ten million to 100 million radioactive particles per month were emitted from the stacks over a period of several months. High activity in the range 0.1 to 3..mu..c was probably confined to large carrier particles of corrosion debris from iron ductwork in the separations plant ventilation air system. This report discusses chemical, physical and radiochemical properties of the particles, and possible biological and health effects of exposure to them. (ACR)
Date: March 22, 1948
Creator: Parker, H M
Partner: UNT Libraries Government Documents Department

General chemistry progress report

Description: This document is a de-classified July 1948 General Chemistry Progress Report from Monsanto Chemical`s Mound facility. Detailed discussions of numerous studies of Postum compounds are included in this report, and experimental data on various chemical and physical properties of these compounds are given.
Date: July 1, 1948
Creator: Barth, S.; Ford, M. & Dismore, P.
Partner: UNT Libraries Government Documents Department

Determination of slug temperatures for various power levels

Description: This study was undertaken to determine the maximum temperatures that may be expected in slugs under various operating power levels. Information of this nature is required to properly evaluate the effects on the slug of pile operation at power levels higher than those currently in use.
Date: January 5, 1949
Creator: Burda, E.J.
Partner: UNT Libraries Government Documents Department

Synthesis of Properties of Methylisoproplydiketone and 1,1 Dinitroisobutane and Their Analytical Determination in Hexone-Nitric Acid Systems

Description: Report discussing a study with the following objectives: "to synthesize pure specimens of both methylisoproplydiketone and 1,1 dinitroisobutane, to determine their physical and chemical properties, and to devise analytical methods which permit their quantitative determination in hexone-nitric acid systems to be encountered in the Redox Process."
Date: August 12, 1949
Creator: Wagner, Robert M.
Partner: UNT Libraries Government Documents Department

Machining & installation of graphite for 105 DR & H

Description: This report describes the basic design, intermediate and final stacking procedures, and graphite behavior of nuclear reactors DR and H during construction. Included in the report are test records to substantiate basic design assumptions and data and the actual performance of the graphite during preliminary and final stacking.
Date: October 1, 1949
Creator: MoKenna, W. R.
Partner: UNT Libraries Government Documents Department

Maximum temperature of aluminum end cap

Description: Neutron density at the end of the slug is increased appreciably and therefore the heat production in the end of the slug is also increased. The end result is increased heat flow into the cap with correspondingly higher temperatures. The combined results and conclusions of documents CP-1580, CP-1989, and CP-2871 afford a means of calculating the aluminum end cap temperatures with consideration being give to the above mentioned {open_quotes}Wilkins effect,{close_quotes} i.e., that the heat production near the end of a slug with an aluminum end cap is greater than the heat production at the middle (axially) of a slug. The maximum temperature in the aluminum end cap is calculated to be about 278{degrees}F. for the {open_quotes}G{close_quotes} Pile. This temperature occurs at the center of the maximum performance process tube.
Date: January 11, 1950
Creator: Roy, G. M.
Partner: UNT Libraries Government Documents Department

Pile Temperature Study

Description: Regarding heat transfer studies of annular spaces around the process tube, there is general agreement among all concerned, that high graphite temperatures are essential at the initial startup. Pile Technology, in studying graphite damage, has developed information that shows little or no expansion occurring when temperatures are maintained at 275{degrees}C. Stored energy levels are less than 5% and K/Ko has saturated in the region of 3.5 to 4. Badly expanded samples (1% increase in length) have recovered 75%. This, of course, is in the pile, since nonlinear annealing is necessary, temperature alone not being sufficient. You may refer to HW-14522, HW-14310 and HW-13117 for further discussion of these points. Based on this assumption we should select some minimum startup temperature, for the edge of the active zone, say 200{degrees}C as a starting point.
Date: January 17, 1950
Creator: Jaske, R. T.
Partner: UNT Libraries Government Documents Department

Physical properties of Hanford metal waste

Description: The Hanford metal wastes were divided into four categories: supernate - the liquid waste; hard sludge - dense agglomerates of poorly defined crystalline carbonates approximating the hardness of soft blackboard chalk; soft sludge - an easily slurried semi-solid consisting chiefly of needle-like phosphates; and recombined sludge - a representative sample of the solid wastes as received from Hanford, shown to be a mixture of hard and soft sludges in the ratio 2/3 by weight. The density of supernate, in the temperature range 24 to 74/sup 0/C, varied from 1.130 to 1.103 g/ml. Hard sludge density averaged 3.0 g/ml and that of soft sludge averaged 1.84 g/ml. The consistency, or apparent viscosity, as a function of temperature, shear rate, and solids content was measured individually on slurries of recombined, soft, and hard sludges using supernate as the suspending medium. Settling rates were also run on these 3 slurries as a function of solids content.
Date: June 29, 1950
Creator: Schilling, C.E.
Partner: UNT Libraries Government Documents Department

Pile graphite expansion

Description: The purpose of this memorandum is to present and analyze, in terms of the current status of knowledge of radiation damage to graphite, the data available at the present time on the expansion status of the graphite in the piles, and suggest, in terms of this analysis, several possibly feasible curative and preventive measures. The portion of the data to be covered in this memorandum consists of that obtained during the last four years from pile motion measurements and from tube bowing measurements, and particularly that from graphite mining operations during the last six months. The objective to be attained is twofold: (1) the information developed here should permit a better understanding of the need for and development of future corrective measures to be applied to the present piles, and (2) this summary will serve as a basis for further experimental work necessary to place the conclusions on a more firm foundation. This memorandum is being issued at this time, although present ideas and conclusions are in a somewhat uncertain state, in the hope that the currently most feasible preventive measure might be applied to the DR Pile before startup.
Date: July 24, 1950
Creator: Warekois, E. P. & Reinker, P. H.
Partner: UNT Libraries Government Documents Department

Some Properties of High-Purity Zirconium and Dilute Alloys With Oxygen

Description: Abstract: A systematic investigation has been made of the physical and mechanical properties of dilute alloys of oxygen in high-purity iodide-refined zirconium. A marked strengthening effect was observed as a result of oxygen additions. Results of tensile tests at elevated temperatures up to 400°C are also presented. Preparation of alloys is discussed in detail.
Date: April 1951
Creator: Treco, R. M.
Partner: UNT Libraries Government Documents Department

The Vapor Pressure and Heat of Vaporization of Bromine Triflouride

Description: The vapor pressure of bromine trifluoride has been measured over the range 39 to 155 C. and the following equation was derived by methods of least squares to represent the experimental data. log{sub 10}P{sub mm} = 7.74853 - l685.8/(t + 220.57). The heat of vaporization was estimated from the following equation which is based upon the Clausius-Clapeyron relation. {Delta}H{sub cal/mole} = 7714 [(t + 273.16)/(t + 220.57)]{sup 2}. In continuation of the program to measure the physical properties of interhalogens, the vapor pressure of bromine trifluoride has been determined. Ruff and Braida (4) measured some of the physical and chemical properties including the vapor pressure over a limited range, 4 to 136 mm. The present investigation extends the vapor pressure data to 2 l/2 atmospheres on material of high purity.
Date: June 8, 1951
Creator: G.D., Grisard J.W. and Oliver
Partner: UNT Libraries Government Documents Department

100 Areas technical activities report - physics, July 1951

Description: This is the monthly 100 areas technical activities report for the physics group for the month of July 1951. This group was concerned with pile related studies. Work discussed includes neutron attenuation measurements in pile shielding test facilities, studies of physical properties of shielding materials (concrete), work on a xenon generator and separation facility, further development and shielding work for a neutron spectrometer, continued work on a magnetic spectrometer, and counting equipment. Studies of neutron fluxes from exponential piles, and criticality studies are also discussed.
Date: August 3, 1951
Partner: UNT Libraries Government Documents Department

Abstract of Paper Presented at the Symposium on Metal ChelateChemistry at Brooklyn Polytechnic Institute on April 26, 1952

Description: The essential structural element which differentiates metal chelate compounds from metal coordination compounds, or metal complexes in general, is the existence of some linkage between two or more of the donor atoms in the first coordination sphere of the metal. It is the purpose of the present discussion to examine the influences that this structural factor may have upon the physical and chemical properties of chelate compounds. Examples of well known, simple coordination compounds involving a variety of donor atoms (Oxygen, nitrogen), as well as a variety of electrostatic situations are shown in the following formula. Below each one are listed a few corresponding chelate structures.
Date: April 1, 1952
Creator: Calvin, Melvin
Partner: UNT Libraries Government Documents Department

Technical activities report - July 1952 graphite development - pile graphite

Description: Physical data are presented for transverse CSF samples with capsule exposures of 568, 1049, and 1617 MD/CT. The higher exposures indicate a sharper damage gradient toward the front of the pile. Additional casings of various types of graphite were loaded into test holes during this month. Average values of the thermal conductivity and electrical resistivity for several types of virgin graphites are presented. Data of this nature will be a regular portion of this report henceforth. Process tube channel 2677-H was mined and traversed for bore diameter. Although several of the tube block junctions were obscured, the channel was quite uniform. Examination of all previously mined graphite powder samples for aluminum oxide corrosion product has been completed and the results are reported.
Date: August 11, 1952
Creator: Music, J. F. & Zuhr, H. F.
Partner: UNT Libraries Government Documents Department

Preparation and Examination of Beryllium Carbide

Description: From abstract: "The properties of beryllium carbide were studied to determine its suitability as a high-temperature refractory. Various methods of preparing it were tried and a number of the physical and chemical properties of the resulting products were determined."
Date: 1953
Creator: Mallett, Manley William; Durbin, E. A.; Udy, M. C.; Vaughan, D. A. & Center, E. J.
Partner: UNT Libraries Government Documents Department

Radiological Sciences Department investigation radiation incident, Class I, No. 299

Description: Fragments of radioactive materials were deposited in the Redox area during August, 1953. By radiation monitoring, the location, physical properties, and dosage were determined. The cause was assumed to be the buildup of ammonium nitrate containing ruthenium on the filters of the Redox stack. The amount of occupational exposure, and the reasons why this incident happened were also discussed.
Date: August 25, 1953
Creator: Ebright, D. P.
Partner: UNT Libraries Government Documents Department

Chemical and Photochemical Reactions of Thioctic Acid and RelatedDisulfides

Description: The carbon cycle of photosynthesis is briefly reviewed in its entirety and the experiments involving it which led to the implication of disulfide rupture in photosynthesis are indicated. A review of the organic, physical and photochemistry of disulfides, with particular reference to the five-membered disulfide rings as they appear in thioctic acid, is given.
Date: June 10, 1954
Creator: Calvin, Melvin
Partner: UNT Libraries Government Documents Department

Nuclear metallurgy lectures: Chapter 1

Description: The purpose of this course is two-fold. It should serve as a review for the metallurgist of the classical metallurgical concepts applied to such metals as uranium, thorium, plutonium, and zirconium. These metals are relatively unfamiliar to the metallurgist, but the concepts are still the same ones applied to familiar metals. The second purpose is to acquaint the non-metallurgist with the reasons for selection, advantages, and disadvantages of the various fuels and structural materials used in a reactor. Thus, there are two purposes: the first is conceptual, and the second is explanatory. A blending of the two must inevitably result in an over-simplification of the metallurgical concepts and an assumption of certain background material which, actually, may not be available to the non-metallurgist. The present lecture is an introduction to the material to be covered. This lecture will have two purposes. The material to be presented in the remaining lectures will be outlined briefly, and the various concepts to be covered in this course will be discussed.
Date: April 13, 1955
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department

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 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. This chapter discusses the mechanical and physical properties of uranium.
Date: May 10, 1955
Creator: Hueschen, R. E.
Partner: UNT Libraries Government Documents Department