Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."

This report has two parts to it discussing mineralogical examination of pitchblende concentrates and nitric acid digest residues. Part I gives the results of a cursory examination with the petrographic microscope of samples of pitchblende concentrates and residues to see if there is a relationship between the mineral composition of the samples and the filterability of the residue. Part II gives a revaluation of the data in Report BMI-241 on the mineral composition of two residues from the nitric acid digestion of pitchblende concentrates at the Rallinckrodt Chemical Works.

From abstract: "The composition of vapors from aqueous nitric acid solutions boiling at 200 mm mercury total pressure is established for solutions containing between - and 67.5 w/o nitric acid. The volatility characteristics of low concentrations of chloride in the same concentration range of nitric acid have been measured in solutions boiling at 200 mm mercury. The effects of chloride concentration and pressure of boiling are evaluated. A spectrophotometric method of the determination of chloride in nitric acid solutions is described."

Report discussing experiments on the interaction of neutron-absorber materials and metal matrix materials used in the fabrication of control rods, such as "boron, cadmium, and some of the rare-earth elements such as gadolinium and europium...In order to evaluate the reactions that might occur during fabrication and use, experiments were carried out in which combinations of the various control materials were heated in intimate contact with the several matrices at elevated temperatures."

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Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]

Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]

The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.

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Abstract: "Formulas are derived for the trajectory of a charged particle in a magnetic field which is a linear function of time. Graphs of certain functions are presented, by means of which a trajectory with given initial position and velocity may be plotted."

From introduction: "This is the first of three articles dealing with the influence of fluorine substitution in the ligand on the properties of metal chelate compounds. Although the primary purpose of this project was to study the influence of fluorine substitution on the properties -- particularly light absorption -- of uranyl compounds, copper chelates were chosen for preliminary study as model substances, because they are easily prepared."

From Abstract: "This paper deals with the vacuum design considerations of large systems involving the application of 8-inch through 32-inch mercury diffusion pumps. The selection, rating, and optimization of pumps are discussed along with the closely allied problem of baffling the pumps. The materials of construction and methods of fabrication to avoid subsequent system contamination are dealt with in detail. System interlocking and its associated instrumentation are illustrated by referral to the operation of a large particle-accelerator vacuum system."

From abstract: "The motion of a charged particle in a region of crossed electric and magnetic fields is discussed... Possible applications of such a system to various problems in nuclear research are suggested and it is shown to be possible in principle to measure the kinetic energy, mass, and ionic charge of various nuclear-reaction products and to separate various short-lived products for rapid examination. Two different devices are proposed. The application of the technique to investigation of the fission process is specifically discussed."

The {open_quotes}O{close_quotes} ring seal has been proposed to replace the van stone flange and the bellows thermal expansion assembly currently used on the existing Hanford piles to achieve water and gas seals, respectively. Possible advantages of the {open_quotes}O{close_quotes} ring seal are: (1) simplification of component parts and elimination of van stone corrosion; (2) simplification of maintenance; (3) lower costs of initial erection; (4) increased strength. This test supplements Test Project No. 27 (a preliminary thermal cycling test) in applying the {open_quotes}O{close_quotes} ring seal assembly to actual pile operating conditions.

The Fuel Development operation at Hanford uses a variety of in-reactor facilities to test experimental and prototypical fuel elements. High pressure-high temperature water loops in constant use are the 6 in. {times} 9 in. ETR core facility, the 3 in. {times} 3 in. ETR reflector facility and four front-to-rear loops in the 100-K East reactor at Hanford. Low pressure water cooled test facilities in use are located in the MTR the various Hanford reactors. Stainless steel sheathed the thermocouples 1/16-inch diameter insulated with MgO or Al{sub 2}O{sub 3} when properly fabricated and installed, will reliably measure in-reactor temperature up to 1000 C and at least 4000 MWD/T exposure. This report provides a brief description of some of the temperature monitored in-reactor experiments.

The objective of the production test is detailed in this report is to obtain information about the behavior of Zircaloy-2 jacketed rod-and-tube fuel elements during irradiation at high coolant temperatures specifically, this test should provide information about fuel element dimensional stability, suitability of the rod and tube support system, and behavior of the uranium--Zircaloy-2 bond. Four co-extended Zircaloy-2 jacketed rod-and-tube elements, two with welded tube end closure and two with integrally extruded tube end closures, will be irradiated to 2500 MWD/T at jacket surface temperatures up to 270{degree}C in the KER loops. One Zircaloy-2 jacketed seven-rod cluster UO{sub 2} element will also be irradiated.

Early in the development of an extended surface fuel element for use in the NPR, several 7-rod cluster fuel elements were irradiated to determine the dimensional stability of such geometries at high burnups. These elements were fabricated from small diameter uranium rods clad unbonded in stainless steel tubes and assembled in a rod cluster geometry by various support devices. Zircaloy clad fuel rods were not yet available, the stainless steel clad rods therefore served as a suitable material which would withstand high temperature water over a long period of time and maintain relatively high strength properties. The purpose of the irradiation detailed in this report was to determine the effect of high exposure on the swelling, dimensional stability, microstructure, and physical properties of uranium rods restrained unbonded in stainless steel. At the same time, this test was designed to evaluate the effect of fuel rods operating in a cluster geometry, to monitor the central core temperature of the uranium, to determine the stainless steel-uranium interface heat transfer bond coefficient, and to determine the average specific power of the assembled element. Goal exposure for this irradiation test was 3500 MWD/t.

This report describes travel to Los Alamos Scientific Laboratory September 17, and 19, ALOO and ACF Industries, Inc. At Los Alamos the principal subjects discussed were reservoir design, and reservoir shipping specifications. In Albuquerque a meeting was held with Albuquerque Operations Office personnel to discuss design and procurement of shipping containers, followed by discussions with ACF of reservoir fabrication and testing.

When a ``K`` type process tube is operated without a slug column, damage may take place in the connector because of the cavitation that originates in the venturi. Reported here is a study of this cavitation problem as related to CG-654 operating conditions. A series of curves were developed to present the effect of the venturi diameter on the venturi {Delta}P for instrument operation and on the cavitation problem at the higher flows which are experienced when the tube is operated without a slug column.

It was agreed at the February, 1951 meeting of the Atomic Energy Commission Technical Information Panel that, wherever practical, progress reports should periodically include a list of previous reports issued in the same series. Such a list would greatly facilitate servicing by installation document rooms since requests are frequently received for reports in a specific series. This report lists the Technical Progress Letters from 1944 to date, and is distributed to recipients of the Letters in accordance with the recommendations of the Panel. Because of its length it was not deemed practical to include it as a part of the report itself. lt is anticipated that it will serve as a reference list and permit reduction of personal files.

In the reference letter and later letters the author made recommendations pertaining to the programs of AEC National Laboratories and other AEC contractors in direct support of the Savannah River project during FY-1956. He believes that these recommendations should now be revised in view of schedule changes ad in the light of accumulated experience. The estimated cost of the programs recommended earlier totaled $2,083,000 for FY-1956. The estimated cost of programs currently recommended total $2,048,000 for FY-1956. The programs mentioned in succeeding paragraphs are concerned mainly with the development of processes for producing extended surface fuel elements and, to a lesser extent, with the development of separations processes. The author considers these particular supporting programs important to the rapid and successful achievement of development objectives at the Savannah River Plant and accordingly recommend that the Commission sustain them. Two of the programs, specifically the work by Sylvania and by Horizons to develop processes for reducing thorium oxide to metal, are not now associated with meeting future production objectives at the Savannah River Plant. The author believes that these programs should be brought to an orderly conclusion, as previously planned, to avoid any loss of the art developed to date.

Prior to fiscal year 1955 waste tank scheduling for Separations Plants included the assumptions that T Plant would cease operations in March, 1955 and B Plant would nto be reactivated. At the beginning of the fiscal year these were changed to the assumptions that T Plant would operate through June, 1958 and B Plant, after reactivation, would operate July, 1955 through June, 1957. It has been necessary to alter waste tank scheduling accordingly. The letter of July 23, 1954, {open_quotes}B Plant Waste Storage Forecast{close_quotes}, outlined the plan for the disposal of wastes from B Plant on the assumption that direct feed of metal waste from B Plant ot the TBP Plant would not be done. On July 30, 1954 this letter was reissued as {open_quotes}Waste Storage for B Plant Reactivation{close_quotes}, with a revision including more details and a provision for the direct feed of metal waste. On August 6, 1954 the letter {open_quotes}T Plant First Cycle Waste{close_quotes} was issued recommending that scavenging of T Plant first cycle waste be started by December 1, 1954. On October 22, 1954 the letter entitled {open_quotes}Justification for T Plant First Cycle Waste Scavenging{close_quotes} gave the detailed economic justification. The present letter summarizes the preceding …