From introduction: This report is a compilation of the presently available data pertaining to the proposed reactor power plant site which may be used in evaluating the proposed measures for protecting the public from possible radioactive hazards, both during normal operation and under unusual hazards.

Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."

From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.

Introduction: Among the many corrosion problems encountered in the production of uranium tetrafluoride and uranium metal from ores and concentrates, some of the most serious occur where hydrofluoric acid must be handled.

Abstract: "The heat-treatment behavior of zirconium alloys containing 7 to 70 w/o uranium is described. The effect of oxygen contamination on the structure and hardness of these alloys is outlined. It is shown that in the initial stages pf transformation of beta zirconium-uranium solid solution into the low-temperature phases a potent hardening reaction occurs in alloys containing 20 to 70 w/o uranium. In this reaction the hardness may rise from 200 DPH characteristic of retained beta to values in excess of 400 DPH. Practical heat treatments have been developed which produce relatively soft alloys. The microstructures and hardnesses produces by these treatments are shown."

Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."

Technical report outlining the theoretical study of the sub-critical BNL (Brookhaven National Laboratory) reactor, and a comparison of reactor performance with the purpose of presenting the experimental results of the experimental methods. Presents experimental results and and a detailed discussion of the experimental methods along with theoretical analysis and evaluation of the results.

Report evaluating different methods of preparing nitric acid solution and different methods of separating plutonium from this nitric acid solution of slag and crucible. Methods are explained and experimental data is given.

This is the monthly report for the Hanford Laboratories Operation, May 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

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: Article 7047a-19 as amended, Admission Tax liability where admission of patron is by sales slip of required amount.

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: Is it incumbent upon the tax assessor of the Skidmore-Tynan Rural High School District No. 36 to prepare the tax rolls and receipts for taxes collected by the Bee County Tax Collector in behalf of such school district, or is the Bee County Tax Collector required to prepare such tax rolls and receipts.

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: Under the Meat Inspection Law, Article 4476-3 Vernon's Civil Statutes, and the General Appropriation Act, may the Department of Health grant compensatory time to inspection employees?

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: In the event an insurance carrier makes a payment to the Second Injury Fund, as provided by Sec. 12c-2(a), Art. 8306, Vernon's Civil Statutes, and a "person entitled to compensation" later proves a valid survivor of the deceased employee, can a refund of the payment to the Second Injury Fund be voluntarily made to the insurance carrier by the Industrial Accident Board.

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: Questions relating to Engineering Fee for Design of Filter Systems for Swimming Pools in three State Parks for the State Parks Board.

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, John Ben Shepperd, regarding a legal question submitted for clarification: Applicability of the State Prize and Award Tax to the "What's My Name" contest.

Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumulated, it will be possible to (1) more accurately evaluate the radiation received by operating personnel, and (2) more accurately (and economically) specify shielding for facilities designed for processing high exposure plutonium. This report gives the results of a gamma energy analysis of the RMA Line and Recuplex obtained with a laboratory model gamma spectrometer. Measurements have been made in the 234-5 Building which have defined the general gamma energy spectrum emitted by the plutonium processing hoods on the RMA Line and in Recuplex. The data obtained from this study has helped resolve the discrepancy between laboratory data and film badge data, and has provided additional information to help in prediction of the gamma radiation levels to be expected from plutonium irradiated to 2000 MWD/T (NPR) and …

Atomic Energy Commission has expressed interest in obtaining xenon with a composite neutron absorption cross section of less than one barn. This material may be obtainable from the off-gas of the Purex dissolver. A proposed gas purification facility would process the Purex off-gas through two distillation steps for isolation of a ``rough`` cut of xenon isotopes containing principally Xe{sup 131}, Xe{sup 132}, Xe{sup 134}, Xe{sup 136}, and a small quantity of krypton. This material would become the feed stream for a thermal diffusion plant for xenon isotope separation. Thermal diffusion has been shown to be the most economical way to concentrate the two heavier xenon isotopes of low cross section and to reject the krypton along with lighter xenon isotopes of high cross section. The objective of the work herein reported was to provide the basis for (l) a scope design of pilot thermal diffusion equipment and (2) design of experiments to be made with this equipment. In the absence of experimental data, the pilot design was developed from theoretical considerations of the parameters considered important in thermal diffusion column operations. It was assumed that the pilot unit would have to provide information on the correlation of theory with practice …

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.

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Slag and crucible can be dissolved satisfactorily by the Los Alamos method of total dissolution with nitric acid in the presence of aluminum nitrate. Extraction of 99% of the plutonium from total dissolution salted with aluminum nitrate was achieved by three successive contactings with 1/10 volumes of 30% TBp- AMSCO 125-90W. The TBPAMSCO phases contacted with leaching solutions salted with calcium nitrate must be scrubbed to remove calcium. Stripping with three 1/10 volumes of 0.1M hydroxylamine sulfate removes 99% of the plutonium from the 30% TBPAMSCO, initially O.lM HNO/sub 3/. Plutonium(III) oxalate, (which could be blended into 234-5 operations) can be precipitated from the aqueous strip solution. It is chemically feasible to recycle slag and crucible solution to the Redox IIA column in amounts up to at least lO% of IIAF by volume. It is also chemically feasible to recycle nitric acid solution of slag crucible obtained in the presence of aluminum nitrate to the Product Precipitation step of the Second Decontamination Cycle of the Bismuth Phosphate Process. (auth)

From introduction: This report is a technical evaluation of four reactor power plant designs proposed by various AEC contractors.

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