The following report describes the developmental process of the determination of free nitric acid in solutions containing uranyl nitrate, aluminum nitrate and sodium dichromate.

A report which intends to acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the radiolanthanum process and to define the terminal status of the design of this laboratory and its equipment.

Introduction: "This report covers progress on the testing of the General Engineering and Consulting Laboratories Turbine Pump No. 1 from May 1, 1948 to Jun 15, 1948. All testing prior to April 30, 1948 has been described in Redox Experiment Testing Report No. 1 (Document HW-9474) and No. 2 (Document HW-9694)."

"This report gives briefly a rather simple method for fabricating foils from uranium buttons. Two log sheets one of a U-238 run and one of a U-255 run are given."

The following report describes a mass flow system that can measure homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, with the addition of considering pressure drops, measuring external to the flow, ruggedness and reliability.

A report which discusses the data submitted for evaluation. This data is about optical densities from infrared spectrometer readings on eight standard samples, ranging in percent TBP from 6.71 to 17.85.

Abstract: "The possibility of transient temperature variations during the self-heating of a plasma by thermonuclear reactions was investigated. Calculations were performed on an IBM Card Program Calculator. Estimates of the time scale for self-heating were obtained. It was concluded that it would be unsafe to assume that the nuclear temperature is always equal to or greater than the electron temperature in a discussion of plasma instabilities for a plasma with 10 percent or greater tritium concentration."

Abstract: "Because of the radiation hazards inherent in processing large volumes of radioactive solutions by solvent extraction techniques, there is need for a system with small hold-up which can be contained within a minimum of shielding and yet which is versatile enough to be used as a research tool. A system utilizing a miniature mixer-settler has been constructed and its successful operation by remote means demonstrated. The unit is semiportable and employs a number of novel features of value in studying a wide variety of solvent extraction flowsheets. Data on the distribution of nitric acid between water and tributyl phosphate (in kerosene) are included as a demonstration of the operability of the unit."

Summary: "The quantity of water adsorbed by graphite at various relative pressures has been determined and the data are presented in graphical and tabular form."

The following report covers mixing k-quantum numbers in Bohr-Mottelson states of spheroidal nuclei.

Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."

The following report is based on work performed under the auspices of the U.S. Atomic Energy Commission. The purpose of this report is to describe an air-core strong focusing synchrotron and its functions.

Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer

This report studies the effect of x irradiation on the maturation of the circulating reticulocytes, using samples of rabbit blood with and without phenylhydresine- or bleeding-induced anemia and comparing them to the blood of human subjects under similar circumstances.

From introduction:"It was the aim of this investigation to determine the resistance of several materials of construction to current and anticipated and anticipated Hanford separation process waste streams under specific conditions. The corrosion rates of mild steel and austenitic stainless steel and the resistance of several commercial protective coatings were established."

Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employed in the tests which could clear the remaining tubes.

"Progress is reported on Phase II of a program for the development of a mixed fission product fueled thermoelectric generator. Materials studies are described in which bonded assemblies of bismuth telluride were life tested up to 3000 hours at 350 to 400 deg F hot junction temperature. Data were too inconsistent to define any satisfactory long-life bonding process. Further work is needed to eliminate the process variables. Insulation studies aimed at determining the thermal conductivity of various insulations with different fill gases under reduced pressures are described. Opacified aerogel powder appears to be very promising as an insulation medium for a diffuse heat source. A full- scale simulated test generator aimed at proving out the concept of a diffuse heat source for power generation is described. Progress on the construction of this electrically heated generator and its thermoelectric power converter is related.

In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentrations detailed neutron balances and a comparison with elementary theory are included. The agreement between the calculated and experimental multiplication constants is excellent for the multigroup calculation but only fair for the elementary calculation. The latter method overestimates the fast leakage so that the computed multiplication constant is less than that found experimentally.

The following report describes data from the continuation of investigations which led to the observation and characterization of five artificial radioactive chains collateral to the natural radioactive families that has lead to the partial identification of one additional chain, collateral to the actinium family.

The following document analyzes the effects of extracting boron from sodium chloride with ethyl alcohol.

"This report was prepared for preliminary use only in the course of work under W31-109 Eng. 52, and the information contained herein may not be correct or in agreement with more recent experimental and operating data. Any values or opinions expressed in the report may only be those of the author, and the General Electric Company makes no representation or warranty (1) as to the value of this report for any purpose or (2) that any use of the report will not infringe the rights of others."

The following report contains papers summarizing the activities of the various sections comprising the Isotope Research and Production Division of Y-12.

Experiments were carried out to determine the erosion, oxidation and dimensional characteristics of purposely defected fuel elements containing unsintered UO2 powder prepared by the swaging technique. The experiments were conducted in an out-of-reactor loop under superheat conditions of pressure, temperature, flow velocity and steam chemical composition.

A report of quarterly results of research and development directed towards establishing new techniques and instruments towards improving present methods for determining levels of radioactivity accurately and safely.