"A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented."

"Magnetic measurements were performance at excitation levels ranging from 4000 to 7600 gauss, to study the dynamic behavior of the magnetic and gradient lengths of the CEA magnet sectors. The influence of the proposed metal vacuum chamber on field and gradient was experimentally determined. Results of measurements made with a 26 in. long grad coil and with small circular grad coils are compared. The reliability of the 26 in. long grad coil is demonstrated."

A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable effect on the handling characteristics, the attack rate on 347 SS, the particle size and crystallite size of the thorium oxide. The attack rate was found to be 1 mpy during the first 100 hours of circulation and decreased to 0.4 mpy at the end of the run.

This technical report summarizes some preliminary calculations of fuel exposures attainable in heterogeneous reactors, fueled with a mixture of thorium and U233, moderated with D2O and operated with no net loss in fissionable fuel.

Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.

For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transuranic elements, and it is with the disposal of these wastes that we are concerned. For technical reasons, we will limit our consideration to the wastes from the processing of solid fuel elements, and from the processing of the very similar solid "blanket" elements in which fissionable fuel is made from non-fissionable isotopes of uranium and thorium by interaction with neutrons in the outer regions of the nuclear reactor.

Thorium nitrate, recovered from irradiated thorium metal processed in the ORNL Thorex Pilot Plant, was converted to thorium oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)

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This report describes the physical description and functions of the capillary flowmeter.

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

Simultaneous reduction of coolant to several or all reactor tubes raises concern not only for the adequacy of protection in the individual process tube but also the reactor as a whole. In event of such flow reduction, the heat generation does not decrease until at least 1.4 seconds have elapsed following the accident. Thus, the water temperature from each tube will rise, and result in an increase in the bulk water temperature. If the increase in bulk water temperature is such that saturation temperature at the top of downcomer is reached, pressurization may occur at that point and exceed the maximum recommended working pressure limit (approximately 1 to 2 psig). The purpose of this report is to present experimental data on a series of tests which were made to simulate flow reductions to a K type process tube by simulated front header pressure decreases.

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High-Temperatare Metallurgy. A series of Inconel loops were operated to study the variation with time of depth of corrosion, effect of flow rate on corrosion, and effect of temperature drop on corrosion using fused salts. The corrosive effects of fused salts on Hastelloy B and Ni--Mo alloys are discussed. A series of Inconel--Na and Inconel-NaK forced circulation loops was operated to study the mass transfer in the systems. The mass transfer between Na and forced circulation loop of stainless steel, Incoloy, and Hastelloys B and W is discussed. Thermal convection loop corrosion resistance studies of Ni--Mo alloy, Inconel castings, and Nb in various systems are presented. Nondestructive testing methods and equipment are discussed. Methods and equipmeat used in the inspection of materials for reactor service are presented. A distillation apparatus is described for the purification of Na. To determine the effect of concentration on the diffusion coefficients, study on the rate of diffusion of NI in liquid Pb was initiated. A study is reported to determine why the protective oxide layer of Nl, Ta, and Zr becomes disrupted. A brief survey was made of the microtopography of sulfide films formed on Nb, Ta, and Zr. A research program was undertaken …

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Disposal of wastes from the processing of solid fuel elements and from solid blanket elements is discussed. The subjects considered include extraction of uranium by several methods, the removal of element jackets, the treatment of uraxium -zirconium fuel elements, disposal into deep wells, the hydraulics of wells, thermal considerations of disposal aquifers regional hydrology, potential deep-well disposal areas in the U. S., aud the cost of disposal. (J.R.D.)

A study was made of the effects of temperature, impurities in the hydrogen chloride, flow rates, and niobium content on both the reaction rates and insoluble uranium losses in the Zircex Process is presented. (W.L.H.)

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A Monte Carlo calculation for computing the diffusion coefficient and diffusion length in a linear system, with alternate solid and void segments is described. The program code is for the IBM 704. (auth)

This report summarizes the design and construction of the Bevatron (6-Bev proton synchrotron) with emphasis on the engineering problems. It includes specifications, outline drawings, and a bibliography of other reports concerning the subject. Operating results and changes made after the initial start-up in February 1954 are mentioned only briefly.

Thorium nitrate, removed from irradiated Th metal processed in the Thorex pilot plant, was converted to the oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)

From introduction: This report details the results of the post-irradiation examination of a test involving one defected rod and one undefected rod.

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: May the Livestock Sanitary Commission of Texas change the location of its headquarters from Fort Worth, Texas, to Austin, Texas, should it so desire, in order to have better accommodations and at less cost, if possible?

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 or not the Comptroller may issue a warrant for funds to be expended at a later date by the Runnels County Water Improvement District or whether or not the Comptroller should require the District to present the accounts to him in the manner required of the other State agencies.

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: Validity of the authorization of a tax sufficient to take care of the maintenance and interest as well as sinking fund recommended by the Commissioners' Court.