This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.

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.

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."

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 is an alphabetical listing of terms and units in common usage at HAPO. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."

From introduction: "The purpose of this report is to summarize some of the observations on the dispersion and rate of disengaging of liquid-liquid systems and suggest some possible lines of future work."

Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."

The following report observes infrared measurements in the region of OH bands, the C2O band vicinity, the low frequency end of the spectrum, and the region of the UO2 band on the system hexone - water - uranyl nitrate.

This report follows work with the purposes of determining the minimum amount of nitric acid required to dissolve slurries of stored metal waste, determining the stability of such metastable solutions as a function of their chemical compositions - primarily acidity - versus time and temperature, and to define a feed suitable for a low-acid TBP process flowsheet, and to indicate the range of variations in composition which can be tolerated for plant operation.

The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.

The following report discusses a method developed by Broida and Moyer, the method describes an emission spectrometer procedure for the determination of the ratio 100 D/(H4D).

From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."

Abstract: The data obtained from the radioassay of fish collected in vicinity of the Hanford Works between April, 1948 and June, 1950 are presented. Most of the radioactivity in the fish resulted from the concentration of p32 in the scales, bone, and certain visceral organs. The level of activity density in the fish was influenced by size, feeding habits and metabolic rate in addition to the activity density of the water. Changes in operation of nuclear reactors have resulted in progressive increases in activity densities of fish from one year to the next. The levels of radioactivity are not sufficiently high to be hazardous to either the fish or persons eating them.

A design study has been made of a graphite superheating reactor, a graphite moderated reactor with a heat rating of 305 Mw which produces superheated steam. It is designed for the production of plutonium and electrical power or for the production of electrical power only. The fuel elements for dual- purpose operation are U metal, while for single purpose action, they are uranium oxide. The fuel elements are cooled by a 7-pass system in which preheated water enters the bottom of the first pass and is discharged as superheated steam at the top of the seventh pass. The reactor control consists of shim control by the gas system, vertical gas-cooled control rods, vertical safety rods, and a ball safety system. Rough cost estimates indicate that the capital cost of the reactor should be comparable to other reactors of similar heat output.

The primary objective of the tests described herein was to determine if the standard five bend connector (drawing H-1-23475) and/or the T. F. Robinson three bend connector (drawing SK-1-20855) fabricated from Type 304 stainless steel tubing would satisfy the requirements of the K reactors. Results of the tests show that the standard five bend connector made from Type 304 stainless steel 0.065 inch wall tubing, in the as bent condition, with either cadmium plated Parker brass nuts and sleeves or cadmium plated high carbon steel nuts and sleeves, is suitable for installation of the K reactors.

A new type of flexible hose connector consisting of a Teflon tube enclosed in a stainless steel wire braid sheath was proposed for use on 105-C rear face in late 1954. A test was initiated to determine the suitability of Teflon, and specifically Fluoroflex Teflon compound for rear face application. Probable useful life limit is estimated at 10⁶ R, which would be attained in about three years in contact with fresh effluent.

Fillerwelding is a fusion welding process that provides for the automatic addition of controlled amounts of fillerwire during inert-gas-shielded tungsten-arc welding. Fillerwelding aluminum jacketed fuel elements has been successfully demonstrated and is being used on a routine basis. This manual was written to provide the necessary information to operate and maintain the fillerweld equipment.

Values of copper tubing pressure drops as determined by test for low flow rates of air, helium, carbon dioxide and water are contained herein. The work was performed in order to provide original data, useful for design work at Hanford Atomic Products Operation, and not available in any known handbook or other publication.

This report constitutes the Quarterly Progress Report covering April-June 1955, for the Health Instruments Division research and development activities. Most of the studies described concern the biological fate, environmental transport of radioactive effluents, or development of instrumentation for radiation detection.

A method for determining the appropriate isotopic content of uranium-235 in uranium slugs has been investigated. In the conduct of the experiment it was found that there was a background counting rate several times the counting rate of the phenomena under study. Methods are suggested for improving the counting rate and reducing the background. The conclusions at this time are that reactivity determinations will provide the most rapid and precise measure of U-235 content in uranium.

Reactivity measurements conducted in the Hanford Test Pile are interpreted to yield resonance integrals for uranium, uranium oxide, thorium and thorium oxide. The experiments were made using cadmium filters and are discussed in terms of the multiplication factor of the Hanford Test Pile.

This report is a manual describing the methods developed by Stokes (1) and Warren and Averbach (2) (3) for the determination of the effects of cold work by x-ray diffraction methods. Only the method of mathematical analysis is presented while the method of obtaining the necessary x-ray diffraction patterns is not mentioned. This manual will be used for an experimental study of irradiation damage to uranium.

A new model High Range Beta-Gamma Survey Instrument, refer to blueprint numbers H-4-2760 and H-4-2761, was designed which utilizes a circuit similar to that of the older model but incorporates three ranges of 0-5 R/hr, 0-50 R/hr, and 0-500 R/hr.

This report describes the results of evaluation tests made on several glass-coated bayonet heaters supplied to Separations Equipment Development by the Pfaudler Company. The glass-coated heaters were found to be resistant to thermal shock, mild mechanical shock, and chemical attack by boiling 60% nitric acid.