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Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
Apparent viscosity of simulated underground metal waste slurries (open access)

Apparent viscosity of simulated underground metal waste slurries

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
Date: June 20, 1950
Creator: Allen, A. W.
System: The UNT Digital Library
Final Summary Safeguards Report For The General Electric Test Reactor (open access)

Final Summary Safeguards Report For The General Electric Test Reactor

This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date: February 20, 1958
Creator: Andersen, R. K. & Jacobs, I. M.
System: The UNT Digital Library
Control of the Dissolved Gases in the Moderator of the HWCTR (open access)

Control of the Dissolved Gases in the Moderator of the HWCTR

The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions of the HWCTR and the solubility of helium in D2O showed that it was possible during normal operation for the helium content of the moderator to exceed saturation and thus for helium to appear as bubbles in the moderator. The possibility of helium bubbles appearing in the moderator because of solubility characteristics was eliminated by modifications to the process system so as to maintain the gas content of the moderator appreciably below saturation.
Date: September 20, 1963
Creator: Arnett, L. M.
System: The UNT Digital Library
Absolute Cross Sections for Secondary Particles Produced in High-Energy Nuclear Bombardments (open access)

Absolute Cross Sections for Secondary Particles Produced in High-Energy Nuclear Bombardments

From abstract: Absolute cross sections for the production of charged secondary particles is the bombardments of aluminum, nickel, silver, and gold by 332-Mev protons, 187-deuterons, and 380-Mev alpha particles have been determined.
Date: April 20, 1956
Creator: Bailey, L. Evan
System: The UNT Digital Library
Approximate Models for Distributed-Parameter Heat-Transfer Systems (open access)

Approximate Models for Distributed-Parameter Heat-Transfer Systems

Summary: The use of dimensionless-parameter frequency response diagrams to determine accuracies of lumped-parameter approximations is demonstrated by two examples: calculation of the heat flux at the surface of a semi-infinite solid due to temperature fluctuations of an adjacent fluid; and the response of a counterflow heat exchanger to inlet fluid temperature perturbations. Dimensionless system parameters make it possible to use general-purpose plots to find the error in particular approximations as a function of the frequency of perturbation. Such plots are directly applicable to control-system stability problems, where the highest frequency of interest is usually apparent.
Date: August 20, 1963
Creator: Ball, S. J.
System: The UNT Digital Library
The Effect of the Speed of Emission on the Rise of a Plume of Stack Gases (open access)

The Effect of the Speed of Emission on the Rise of a Plume of Stack Gases

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.
System: The UNT Digital Library
Techniques for Estimating the Specific Retention Properties of Hanford Soils (open access)

Techniques for Estimating the Specific Retention Properties of Hanford Soils

Disposal on a specific retention basic of certain radioactive liquid waste solutions emanating from separations from separations plants has been practiced at Hanford since 1944. As used at Hanford, the term "specific retention" is defined as that volume of waste liquids that may be disposed to the soil* and be held against the force of gravity by the molecular attraction between sand grains and the surface tension of the water, when expressed as percent of packed soil volume. In practice it represents the volume of liquid that may be discharged to a disposal pit of known dimensions without leakage to the ground, water, expressed as percent of the total volume of a column of soil with the same cross section as the pit, and extending from the bottom of the pit to the water table. It is recognized that some degree of lateral spreading will occur which has the effect of enlarging the volume of soil contacted by the liquid.
Date: August 20, 1959
Creator: Bierschenk, William H.
System: The UNT Digital Library
Minutes of the Conference of Linear Accelerators for High Energies (open access)

Minutes of the Conference of Linear Accelerators for High Energies

During the past year notable progress was made in several laboratories on design for linear accelerators in the energy range up to and above 1 Bev. Interest in linacs for this energy centers on two possible applications: first, as injectors for 300 to 1000 Bev synchrotrons, and second, as sources of intense meson beams. To review this progress, a conference jointly sponsored by the Brookhaven National Laboratory and Yale University was held at Brookhaven during the week of August 20, 1962.
Date: 1962-08-20/1962-08-24
Creator: Blewett, J. P.; van Steenbergen, A.; Knowles, H. B.; Ohnuma, S. & Sinclair, C. K.
System: The UNT Digital Library
Aqueous Uranium Slurry Studies (open access)

Aqueous Uranium Slurry Studies

A summary of the laboratory development program on aqueous uranium slurry fuels for the Homogenous Reactor Project during the period April 1951 through March 1953 is presented. These investigations were devoted primarily to a study of the uranium oxides in aqueous suspensions. It was concluded that U(VI) was most likely to be the stable valence state in such slurry fuels and it was shown that β-UO3·H2O platelet crystals were the stable modification at 250°C. Very pure slurries of β-UO3·H2O platelets, uranium concentration of 250g/liter and average particle size of about 10 μ, had favorable settling rates and could be easily redispersed. Their viscosity and corrosion rate in stainless steel were comparable with those in water. Exposure of these slurries to pile radiation disclosed that radiolytic hydrogen and oxygen gas pressure comparable in magnitude to those of uncatalyzed uranyl sulfate solutions could be expected. Fission products in the irradiated slurries were predominantly associated with the solids. Radiation also tended to promote caking of these solids on the walls of the radiation bombs. Uranyl phosphate and the magnesium uranates were briefly investigated as alternate system but were not found satisfactory. The program was discontinued before the feasibility of uranium slurries for reactor …
Date: October 20, 1955
Creator: Blomeke, J. O.; Bamberg, J. L.; Blomeke, J. O.; Bruce, F. R.; Fulmer, J. M.; McBride, J. P. et al.
System: The UNT Digital Library
Purex Pulse-Column Studies With Unirradiated Uranium: (Development of Specifications for the O.R.N.L. Pilot Plant) (open access)

Purex Pulse-Column Studies With Unirradiated Uranium: (Development of Specifications for the O.R.N.L. Pilot Plant)

Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.
Date: February 20, 1951
Creator: Bradley, J. G.
System: The UNT Digital Library
Investigation of Local Boiling of SM-1 (open access)

Investigation of Local Boiling of SM-1

Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of primary pressure or inlet temperature to introduce the phenomenon of nucleate boiling in the the core. Reduction of system pressures to 1000, 800, and 600 psia and increasing core inlet temperatures to 465 and 500 degree F were studied as the means to induce boiling in the core. This analysis indicates that SM-1 Core I Rearranged and Spiked can be safely operated at the reduced pressure of 910 psia without introducing extensive boiling in the core. SM-1 Core II with Special Components can be operated at 800 psia or at an inlet temperature of 500 degree F at 1200 psia.
Date: June 20, 1961
Creator: Bradley, P. L.
System: The UNT Digital Library
Modified-Graphite Technology : Quarterly Report No. 1 (open access)

Modified-Graphite Technology : Quarterly Report No. 1

From abstract: "This report summarizes the past year of study of fine, molded, multicrystalline graphites with particular reference to the interrelation among certain properties with the composition, fabricating techniques, and thermal treatments found to influence them."
Date: January 20, 1960
Creator: Bradstreet, Samuel W.
System: The UNT Digital Library
The Effect of Impurities Upon Sulfide Refractories (open access)

The Effect of Impurities Upon Sulfide Refractories

Abstract. A summary of the effect of metal, carbon, silicon, and oxygen impurities upon the various sulfide refractories is given and the proper procedures for elimination of the impurities are discussed. CeS which is properly prepared can be handled in air without danger of catching fire or appreciable oxidation. 650 satisfactory crucibles have been made to date using sulfides which were screened and pressed in air with less than 0.5% oxygen pickup. The other cerium and thorium sulfides are even more inert to oxidation than is CeS. Phase diagram possibilities are discussed for the cerium and thorium sulfide and oxy-sulfide systems. Further study of the ThS has shown that ThS crucibles are the highest melting and least volatile of the sulfide crucibles and ThS may be used for remelting of some metals up to 2000 degrees C. ThS crucibles appear to be the most suitable containers for metal reductions.
Date: January 20, 1945
Creator: Brewer, L.; Bromley, L. A.; Gilles, P. & Lofgren, N.
System: The UNT Digital Library
The Higher Fluorides of Plutonium (open access)

The Higher Fluorides of Plutonium

A systematic set of thermodynamic data for most of the known compounds of plutonium is presented. From earlier data present, it is now possible to extend the tabulation of data for the compounds of plutonium to include PuF(4), PuF(5), and PuF(6).
Date: March 20, 1950
Creator: Brewer, Leo, 1919-2005; Bromley, LeRoy A.; Gilles, Paul W. & Lofgren, Norman L.
System: The UNT Digital Library
The Analysis of TBP Process Streams for Calcium with the Flame Photometer (open access)

The Analysis of TBP Process Streams for Calcium with the Flame Photometer

Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.
Date: February 20, 1953
Creator: Brite, D. W.
System: The UNT Digital Library
Equation of State and Heat Content of Uranium (open access)

Equation of State and Heat Content of Uranium

Report issued by the APDA regarting studies conducted on the state of uranium at different temperature and pressure. Calculations are presented for the differing pressures of uranium; it includes tables.
Date: February 20, 1957
Creator: Brout, Robert H.
System: The UNT Digital Library
Investigation Of Windows And Shields For Neutron Point Sources (open access)

Investigation Of Windows And Shields For Neutron Point Sources

An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date: May 20, 1959
Creator: Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
System: The UNT Digital Library
Feasibility Study of a New Mass Flow System : Quarterly Report No. 3 Covering the Period from December 1, 1960 to February 28, 1961 (open access)

Feasibility Study of a New Mass Flow System : Quarterly Report No. 3 Covering the Period from December 1, 1960 to February 28, 1961

This is the third quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: March 20, 1961
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
System: The UNT Digital Library
Magnetic Field Distributions in a Pinched Discharge (open access)

Magnetic Field Distributions in a Pinched Discharge

By use of small magnetic probes inserted into the discharge, the magnetic field distributions in the interior of a high-power pinched discharge have been measured as a function of time. From these data the current distributions can be deduced. By applying a static pressure calculation, in the cases when the radical pinch accelerations are small, the plasma pressure nkT in the pinch has been determined, with superimposed axial magnetic fields, and for stable and unstable configurations.
Date: November 20, 1956
Creator: Burkhardt, L. C.; Lovberg, Ralph H. (Ralph Harvey) & Phillips, J. A.
System: The UNT Digital Library
The Behavior of Some Solid Materials Under Pile Operating Conditions (open access)

The Behavior of Some Solid Materials Under Pile Operating Conditions

Technical report abstract. The present state of knowledge concerning the effect of pile radiation on a variety of solid materials is reviewed. Radiation corrosion will not be a serious hazard for aluminum or stainless steel but it can be for iron or lead if either are exposed to water. Apart from corrosion the principal uncertainty is in regard to the Wigner effect on the behavior of metals. There is at present no ground for optimism regarding the behavior of tuballoy. The effect on aluminum or a bonding material while less severe must also be considered serious. The expectation in regard to graphite is that its behavior will not cause trouble during the first 100 days of operation although serious troubles will probably arise within two years of operation. Organic materials can be used safely only in regions of limited exposure.
Date: July 20, 1944
Creator: Burton, Milton, 1902- & Seitz, Frederick, 1911-2008
System: The UNT Digital Library
The Production of Ceramic Ware by Slip-Casting (open access)

The Production of Ceramic Ware by Slip-Casting

This report discusses the production of ceramic ware through the process of slip-casting. The report separately describes the processes of creating zirconia ware, beryllia ware, alundum ware, thoria ware, and specially shaped ceramic ware.
Date: October 20, 1945
Creator: Calderwood, Wayne
System: The UNT Digital Library
Artificial Radioactive Isotopes of Cerium and Lanthanum (open access)

Artificial Radioactive Isotopes of Cerium and Lanthanum

The following document describes some studies of the radioactive isotopes of cerium and lanthanum lying on the light or neutron-deficient side of stability.
Date: July 20, 1948
Creator: Chubbuck, James B.
System: The UNT Digital Library
Ferrous Sulfamate Stability in the RA System (open access)

Ferrous Sulfamate Stability in the RA System

Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."
Date: April 20, 1950
Creator: Clagett, Fred
System: The UNT Digital Library