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)

A number of conceivable reactivity accidents were analyzed, using conservatively pessimistic assumptions and approximations, to permit evaluation of reactor safety. Most of the calculations, which are described in detail, were performed by a digital kinetics program, MURGATROYD. Some analog analyses were also made. None of the accidents which were analyzed lead to catastrophic failure of the reactor, which is the primary consideration. Some internal damage to the reactor from undesirably high temperatures could result from extreme cold- slug accidents, premature criticality during filling, or uncontrolled rod withdrawal. Each of these accidents could happen only by compounded failure of protective devices, and in each case there exists means of effective corrective action independent of the primary protection, so that damage is unlikeIy. The calculated response to arbitrary ramp and step additions of reactivity show that damaging pressures could occur only if the addition is the equivalent of a step of about 1% delta k/k or greater. (auth)

Research and development of water-cooled reactors are reported including work on EBWR and BORAX-V. Work on liquid metal cooled reactors is also reported in sections on general research and development, EBR-I and II, aud FARET. Other work is reported on genenal nuclear technology and advanced systems development. (J.R.D.)

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.

The following activities were conducted during the month of April 1969: continued effort toward completion of the detailed design of the PMC-2 converter, conducted technical liaison with Westinghouse with respect to the power cable specification, conducted potting test for evaluation of material suitable for SNAP-23A converter PMC-2 leak specification, and completed design of parts for the Weld Development Program. Test data evaluation and analysis were performed on the following long-term test devices during February 1969: experimental mockup converter No. 2 (EMC-2), experimental mockup converter No. 3 (EMC-3), prototype mockup converter No. 1B (PMC-1B), 10-couple modules 1 and 3, 10-couple modules 5 through 12 on design-of-experiments tests, 6-couple module 23A3, and converter 23 P-2.

This is the monthly report for the Hanford Laboratories Operation, April 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

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.

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.

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, Crawford Martin, regarding a legal question submitted for clarification; Whether a District Clerk can serve as a reciever in a case pending in the court of which he is the clerk.

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, Crawford Martin, regarding a legal question submitted for clarification;The legality of a state department head's decision to withhold insurance premium payments from the for salaries of employees for only one insurance company.

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, Waggoner Carr, regarding a legal question submitted for clarification: Under the submitted facts, whether the Gross Receipts Tax provided for by Article 11.03m Taxation-General, is due by the stated corporations.

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, Waggoner Carr, regarding a legal question submitted for clarification: Exemption from franchise tax of non-profit corporations under submitted facts.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether the State Building Commission may enter into certain contracts with other state agencies and have certain funds appropriated to such agencies transferred to the Building Commission for payment of services under such contract.

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.

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.

The major technical bases for the FFTF first core fuel assembly conceptual design are presented in four general categories: (1) thermal, (2) hydraulic, (3) structural and (4) performance-manufacturing design characteristics. Recommended design values and conceptual engineering drawings of the fuel pin and subassembly are included .

In Part One they formulate in a general way the problem of analyzing and evaluating the aberrations of quadrupole magnet beam systems, and of characterizing the shapes and other properties of the beam envelopes in the neighborhood of foci. They consider all aberrations, including those due to misalignments and faulty construction, through third order in small parameters, for quadrupole beam systems. One result of this study is the development of analytic and numerical techniques for treating these aberrations, yielding useful expressions for the comparison of the aberrations of different beam systems. A second result of this study is a comprehensive digital computer program that determines the magnitude and nature of the aberrations of such beam systems. The code, using linear programming techniques, will adjust the parameters of a beam system to obtain specified optical properties and to reduce the magnitude of aberrations that limit the performance of that system. They examine numerically, in detail, the aberrations of two typical beam systems. In Part Two, they examine the problem of extracting the proton beam from a synchrotron of 'H' type magnet construction. They describe the optical studies that resulted in the design of an external beam from the Bevatron that is …

This is the monthly report for the Hanford Laboratories Operation, April, 1963. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, applied mathematics operation, programming, and radiation protection operation discussed.

Instrumentation studies and the Hazards Review have demonstrated the need for instrumentation which will scram the reactors if the exponential rate of power increase is excessive. A development program has demonstrated the feasibility of such a system. This document defines the program necessary to provide Intermediate Range exponential rate protection in the safety circuits of five reactors, provides justification for the project, and presents estimates of the cost and schedule required to accomplish the program.

Considerable interest has been generated concerning the recent series of overbore fuel failures at C Reactor. It therefore is appropriate to document the operating conditions which existed prior to the failures. This report presents a chronological description of events leading up to the failures, and graphs and tables of various pertinent parameters.

The choice of materials and other vessel design decisions necessary to provide the desired life expectancy for the FTR vessel are partially dependent upon estimates of the number and type of reactor shutdowns and startups which may be anticipated. Current estimates of these so-called "cycles" are given, including scram frequency, experimental outage frequency, standard shutdowns and startups, and rapid controlled shutdowns. Also discussed are abnormal heatup or cooldown, and tentative goals for temperature controls. MTR, ETR, and typical PRTR operating histories are tabulated.

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.

Abstract: Various methods and techniques of measuring void fractions in boiling heat transfer media are discussed.

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