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Research and development progress is reported on analytical instrumentation, chemical analysis of advanced reactor fuels, analytical studies of molten-salt systems, special research problems, reactor projects, effects of radiation on analytical methods, x-ray and spectrochemical analyses, spectroscopy, optical and electron microscopy, nuclear and radiochemical analyses, inorganic preparations, organic preparations, and analytical development. Service analyses are also described. Separate abstracts were prepared for each topic. (M.C.G.)

The equations and procedures of the PTD-1 program for obtaining the surface temperature distribution, the gas bulk temperature, and the pressure distribution for any of the 234 channels in the EGCR are developed. The program, in FORTRAN for the IBM 7090, is designed for any arbitrary power distribution yielding a constant gas outiet temperature or a given maximum surface temperature and includes the effects of thermal radiation on surface and bulk gas temperatures. The flow sheet and some results are included. (auth)

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Reliable line disconnects are necessary to permit the remote replacement of process equipment in the Transuranium Processing Facility. Two disconnect designs were subjected to several severe tests in order to select the most suitable design. These performance tests demonstrated the superiority of the surface-seal concept over that of the line seal-concept and the reliability of this seal when subjected to misalignment forces, corrosive solutions, rough handling and interchange of mating parts. Tests of Hastelloy C disconnects after heat treatment demonstrated the necessity for joining the disconnect to the process tubing by means other than welding. Several leak-tight joints were made by external mechanical swaging, by external electrical swaging (by the Magniform'' process developed by the General Dynamics Corporation) and by internal rolling. Hastelloy C disconnect samples machined to reasonable machine tolerance established the economic feasibility of the design. (auth)

"An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."

This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.

Modification of an earlier program to remove restrictions in calculating the short or long great circle path.

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The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth)

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The theoretical and practical aspects of the accelerating mode (TM01) in iris-loaded waveguides have been covered extensively in many reports and publications. The pulse shortening observed in linacs and the possible application of an iris-loaded waveguides as the deflecting structure for rf particle separators stimulated the interest in the nature of higher order modes. Some experimental results on higher order modes in iris-loaded waveguides are available in references. Results of studies done at CERN are not yet published; they were however communicated to the authors and represented the basis of work done at Brookhaven. A preliminary account of BNL results was given in reference. The purpose of this report is to describe the model measurements which were necessary to determine the geometry of a brazed or electroformed prototype for a deflecting waveguide. At the same time, a systematic investigation of other than the deflecting mode was done to ensure a nondegenerate field solution at the operating frequency. The measurements are compared with computational results obtained on the IBM 7090 at BNL.

This document is the January 1969 monthly report for Hanford Categories C-57 and C-65. It covers reactor plant operation, fuel and target fabrication, irradiation services, and technical activities at the Hanford C, N, and K reactors. It features an evaluation of an incident at the KW reactor.

The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.

An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development eIforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, ldaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes. Bulk densities of 0.8 g/cc were increased to 2.9 g/cc by selective use of fluxes and cold compacting techniques. This means that power densities of up to.001 w/cc will …

The natural exponential decay of a radioisotope used as a heat source for a thermoelectric generator makes the use of a power flattening'' device highly desirable, especially when the duration of the mission is large compared to the half life of the radioisotope. Power-flattening devices are considered which either dump excess heat outside the thermoelectric generator or use the characteristics of the generator to absorb the excess heat and thereby regulate the hot junction temperature. A number of power-flattening devices were studied both analytically and experimentally with a view toward operability in space. The most promising concepts are (a) to utilize a secondary radiator of variable area; (b) to provide thermal shunts that are sequentially removed during the mission; (c) to use a secondary radiator coupled to the heat source through a slowly evaporating thermal connection. (auth)

This report details test plans for production test IP-560-A. The objective of which is to determine the corrosion effects resulting from reducing the amount of sodium dichromate corrosion inhibitor added to process water from 1.8 to 1.0 ppm at a process water pH of 6.6.

A resume of Health Physics activities for October, November, and December, 1959 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental serveys are included.

Radiometric methods of analysis for magnesium and calcium have been developed as part of a program for the U. S. Atomic Energy Commission. Office of Isotopes Development, which are applicable to the determination of these elements in portland cement Both methods employ, as a precipitant, a standard solution of (NH/sub 4/)/sub 2/HPO/sub 4/ labeled with phosphorus-32. In the presence of NH/ sub 4/OH, this reagent precipitate; MgNH/sub 4/PO/sub 4/ or Ca/sub 3/(PO/sub 4/)/ sub 2/ from a solution of magnesium or calcium ions. The reduction in the radioactivity level of the labeled phosphate solution after precipitation serves as a measure of the phosphate reacted and thus a measure of the quantity of magnesium or calcium present. Studies have been made of the effects of reagent concentration, NH/sub 4/OH concentration, and other experimental variables. The interference of other elements present normally in portland cement and its raw materials has been determined. The concentration ranges for highest accuracy have been found to be 5 to 15 mg of MgO per 100 ml and 15 to 30 mg of CaO per 50 ml. (auth)

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This report is a request to ship depleted Uranium Oxide to the Hanford Reservation.

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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: Procedure for nomination of candidate for Associate Justice of the Court of Civil Appeals, Ninth Supreme Judicial District, under the stated facts.