States

Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development (open access)

Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development

Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added to the combined wash solution and filtrate produced during the precipitation step to destroy the formate ion (which inhibits uranium extraction) and to prevent post-precipitation during the evaporation of these solutions. The other flowsheet calls for addition of sufficient nitric acid to destroy the formate ion, but not enough to prevent post- precipitation during the concentration step. Post-precipitation removes additional zirconium and fluoride, but necessitates an additional solids- separation step. (auth)
Date: May 15, 1962
Creator: Newby, B. J.
Object Type: Report
System: The UNT Digital Library
XNJ140E Nuclear Turbojet, Section. 4 Reactor (open access)

XNJ140E Nuclear Turbojet, Section. 4 Reactor

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company.
Date: May 15, 1962
Creator: Layman, D. C.
Object Type: Report
System: The UNT Digital Library
Atomic and molecular collision cross sections of interest in controlled thermonuclear research (open access)

Atomic and molecular collision cross sections of interest in controlled thermonuclear research

A graphical compilation is presented of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are shown, as a function of energy, for collision processes involving molecular ion dissociation, charge exchange, excitation, ionization, photoionization, scattering, energy loss, and recombination. Pertinent nuclear cross sections are also included. A bibliography is given covering the literature since 1950. (auth)
Date: May 15, 1961
Creator: Barnett, C. F.; Gauster, W. B. & Ray, J. A.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, October-December 1960 (open access)

Chemical Processing Technology Quarterly Progress Report, October-December 1960

ICPP Operations. Changes made in processing equipment are described, and the use of continuous steam stripping to free waste solvent of Pu is described. Agueous Processing Studies. Studies were made of methods for separating Zr from dissolver solutions of U-Zr alloys. Recovery of U from BeO/ sub 2/-UO/sub 2/ ceramic fuels by grinding-leaching technique using boiling HNO/ sub 3/ reached 75 to 80%. Waste Calcination. Test results of feed spray nozzles for use in the Demonstrational Waste Calcining Facility are given. Studies were made on the calcination of aluminum nitrate and zirconium fluoride waste solutions. Waste Treatment. Removal of Cs and Sr from wastes by adsorption was investigated. The conditions for optimum separation of Fe, Ni, and Cr by Hg cathode electrolysis from waste solutions resulting from processing of stainless steel reactor fuels were determined. Electrolytic Dissolution Systems. The electrolytic dissolution of type 304 stainless steel was studied in the transpassive region as a function of electrode potential and HNO/sub 3/ concentration. An analog simulation study of an electrolytic dissolver is described. A niobium cathode in an electrolytic dissolver dissolving stainless steel in boiling HNO/sub 3/ did not absorb H/sub 2/. The corrosion resistance of several container materials to 1 …
Date: May 15, 1961
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand (open access)

Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand

Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H for the reaction was found to be approximately 0. The rate constant, k1 was 2.3 x 10-5 sec.-1 at 25 degree C and it was nearly independent of ionic strength. The acid hydrolysis provides a mechanism for the exchange of the chloride ligand and Cl-. Exchange experiments with Cl36 showed that in addition to the acid hydrolysis, a process, first order in both, [Pt(NH3)3Cl] and Cl- with a rate constant of 6. 10-5 sec.-1M.-1 contributes to the exchange. The behavior of the entire series of chloro-ammines of platinum(II) toward acid hydrolysis and chloride exchange has been summarized, and a likely mechanism for the process has been discussed.
Date: May 15, 1961
Creator: Aprile, Ferruccio. & Martin, Don S., Jr.
Object Type: Report
System: The UNT Digital Library
DISSOLUTION OF URANIUM OXIDES FORMED DURING A FUEL ELEMENT FAILURE (open access)

DISSOLUTION OF URANIUM OXIDES FORMED DURING A FUEL ELEMENT FAILURE

Laboratory and pilot plant work directed toward development of decontamination methods for high-temperature pressurized water systems are deseribed. It is noted that failure and corrosion of metallic U fuel elements in such systems produces uranium oxides wofth a large percentage of fission products remaining assoeiated with the oxide particles. Decontamination requires dissolution and/or flushing of these oxides from the system. A summary of spceific tests involving promising solutions is presented. (J.R.D.)
Date: May 15, 1961
Creator: Neibaur, G. E. & Stice, N. D.
Object Type: Report
System: The UNT Digital Library
Hanford Laboratories Operation monthly activities report, April 1961 (open access)

Hanford Laboratories Operation monthly activities report, April 1961

This is the monthly report for the Hanford Laboratories Operation, April 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: May 15, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Hydraulic demand curves for BDF geometry with enlarged outlet fittings: 25 PSIG rear header pressure (open access)

Hydraulic demand curves for BDF geometry with enlarged outlet fittings: 25 PSIG rear header pressure

The purpose of this report is to present steady state hydraulic demand data for BDF type process assembly with specific enlarged outlet fittings and to compare these data with previous correlations of hydraulic demand for a BDF assembly with standard outlet fittings.
Date: May 15, 1961
Creator: Waters, E. D. & Fitzsimmons, D. E.
Object Type: Report
System: The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs (open access)

Investigations of Neutron Penetration in TiH and Steel Slabs

Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date: May 15, 1961
Creator: Karcher, R. H.
Object Type: Report
System: The UNT Digital Library
Irradiation Processing Department Monthly Report: April 1961 (open access)

Irradiation Processing Department Monthly Report: April 1961

This document details activities of the irradiation processing department during the month of April, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; Financial Operation; and NPR project.
Date: May 15, 1961
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Object Type: Report
System: The UNT Digital Library
Preprocessing of Procedure in the ORACLE-Algol Translator (open access)

Preprocessing of Procedure in the ORACLE-Algol Translator

This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on the use of procedures. The result, however, retains the more basic features of the Algol 60 procedure concept. Most of the algorithms published in the Communications of the Association for Computing Machinery can be handled by the preprocessor with few minor or no changes.
Date: May 15, 1961
Creator: Bumgarner, L. L.
Object Type: Report
System: The UNT Digital Library
Report on the projection welded brazed closure for Zircaloy-2 clad fuel elements (open access)

Report on the projection welded brazed closure for Zircaloy-2 clad fuel elements

The projection welded brazed closure is being studied as a possible alternate method of closing coextruded Zircaloy-2 clad uranium fuel elements for the NPR. This closure consists essentially of projection welding the Zircaloy-2 cap to the element cladding followed by a fast resistance heating of the cap and exposed uranium face under pressure to braze the cap to the uranium face. The work to date has been entirely on 0.593 inch OD rods and 1.050 inch OD by 0.500 inch ID tubular elements. This closure has the advantage that the entire closure is completed in less than 5 seconds on one machine and consequently the element is at a temperature which would be detrimental to the Zircaloy-2 cladding and uranium bond for a very short time. The amount of uranium removed for this closure is reduced by a factor of 10 over conventional braze closure methods with a substantial savings in uranium and acid milling time. A braze material which is not toxic can be used to bond the cap to the uranium.
Date: May 15, 1961
Creator: Ard, P. A. & Steinkamp, W. I.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1055 (open access)

Texas Attorney General Opinion: WW-1055

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the placing of the file mark of the County Clerk on a subdivision plat or map of a subdivided tract of land located in the county but not within five miles of an incorporated town, without the authorization of the County Commissioners' Court constitutes an acceptance by the County Commissioners' Court of the road system set forth in the plat or map as a part of the county road system.
Date: May 15, 1961
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1058 (open access)

Texas Attorney General Opinion: WW-1058

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether funds derived from a mineral lease on land deeded to the County Judge of Wise County for use as a cemetery may be used by the Commissioners Court of Wise County for general county purposes.
Date: May 15, 1961
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Niobium Phase Diagrams (open access)

Niobium Phase Diagrams

The following report is the final technical report on a series of reports under contract AT(11-1)-515, titled "Niobium Phase Diagrams", covering the period from April 15, 1957 to April 16, 1960.
Date: May 15, 1960
Creator: Elliott, Rodney P. & Komjathy, Steven
Object Type: Report
System: The UNT Digital Library