A summary ls presented of the off-slte radiological safety actlvities of the U. S. Public Health Service during the Project Gnome operation. Topics dlscussed include: operational procedures; collection of data by aerial monltoring, mobile monitoring, potash mlne surveys, air sampling, milk sampllng, water sampling, soil and vegetation sampllng, and a film badge program; laboratory control, emergency measures; medlcal services; and veterinary activltles. It was concluded that no persons ln the vlclnlty of the Gnome test site recelved harmful amounts of radlation either lnternally or externally. (M.C.G.)

Methods of determining the fate of radioactive fuels in space power units burned up on re-entry into the earth's atmosphere are reviewed. Particulate characteristics experiments were derived from an analytical study on the ablation of Dlutonium fuel. This study revealed that the particulate size distribution resulting on re-entry burnup is a function of: the fuel form in use and the material velocity and atmospheric density at the time the fuel is exposed. The particulate fate experiments were derived essentially from studies of the effects of thermal and turbulent diffusion, and wind and gravity dispersion on the particulate cloud. The experiments recommended are described. (M.C.G.)

The radiochemistry of cobalt is discussed. Included are a review of the nuclear and chemical features of cobalt, a discussion of problems of dissolution of a sample and counting techniques, and a collection of radiochemical procedures for the element as found in the literature. (M.C.G.)

The design of the Army Reactor PL refueling equipment is described. Details of refueling procedures are also given along with a definitive hardware design for the radioactive gas handling equipment which is described in report IDO19030. (J.R.D.)

The instellation is designed primarily for operational testing of Na- heated steam generators and intermediate heat exchangers suitable as prototype components for large, Na-cooled power plants. Other types of Na components can also be tested in the facility. The instellation consists of a 35-Mwt gas-fired Na heat source, a main primary-Na system, a main secondary-Na system, a water- steam system, and a set-up for heat rejection to air. (J.R.D.)

An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)

A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)

A review of the nuclear and chemical features of uranium is presented. The problems of dissolution of a sample and counting techniques are discussed. A collection of radiochemical procedures for the element as found in the literature is included. (M.C.G.)

The SNAP-8 Electrical Generating System is a nuclearturbo-electric space power plant -which is ideally suited for utilization with electric propulsion. Several applications, the program objectives, the over-all system, and the design of the major components are described. The program status is delineated and future plans leading to an early flight test and equipment endurance demonstration are defined. (auth)

Nitrosyl and fluoride ions are formed in liquid anhydrous hydrogen fluoride when nitric oxide, nitrogen sesquioxide, nitrogen tetroxide, or nitrosyl fluoride, are dissolved. Vapor infrared analysis was used to study the solution composition and gaseous reaction products. These solutions react with metallic uranium, plutonium, zirconium, iron, and aluminum, as well as ceramic uranium oxide and uranium carbide, forming soluble nitrosyl metal fluoride complexes and liberating nitric oxide. The uranium compound identified as nitrosylium hexafluorouranate, NOUF/sub 6/, was made volatile by passing nitrosyl fluoride gas over the dry salt at 500 deg C. (auth)

A new suggestion is made based on model work associated with similar measurements on the biological material itself. The primary quantum conversion act is an ionization occurring in a charge transfer complex. This is what it amounts to in chemical terms. But this process cannot occur in isolated charge transfer molecules in solution because the products cannot escape from each other. The primary quantum conversion as it occurs in modern photosynthesis can only take place in a laminated structure where the electrons and holes can escape from each other by electron migration and not by atomic migrations. This is the essential feature introduced here which differs from all the previous notions of how quantum conversion occurs in chemistry or biology.

None

The following report is the ninth in a series of monthly reports covering the program with the objective of developing alloys having superior 680 F water and/or 750 to 900 F steam corrosion resistance, as well as developing higher strength alloys for current temperature ranges while still maintaining corrosion resistance comparable to that of Zircaloy-2. This report was made covering the period December 1 to December 31, 1960.

This report presents a planned reactor test program in support of the research and development study to investigate the formation of radioisotopes in reactor cooling water and to devise means of reducing the amounts of those radioisotopes formed which result in significant exposures to downstream users of the Columbia River water. The effects of water treatment process changes and reactor operation on the formation of radioisotopes of radiological interest will be studied utilizing four of the 1706-KE single-pass tubes together with special demineralizer and water treatment facilities to be obtained in 1961. Specially treated water containing no salts, single salts, mixtures of salts, special additives, and complexing agents will be investigated. The effects of varying water composition and pH, of using aluminum and zirconium reactor tubes, and of varying reactor conditions of tube outlet temperature, water flow rate, flux, and power level will be tested. 1 ref.

None

This document details activities of the Irradiation Processing Department during the month of December 1961.

This document details the monthly activities of the Reactor Branch for the period of January 1960 through December 1960.

The Birch Plant Improvement Program is described in this document. This program was instituted to fully support the AEC program for maximum recovery of neptunium from current separations feed material and other sources as the AEC may consider appropriate to their needs for increasing the availability of neptunium.

This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe loadings at H Reactor. There is calculated decrease in buckled-zone (E-metal blanket) conversion ratio of 13% in the E-N loading as compared to normal fringe loadings; this loss is due to the effective reduction in pile size due to the presence of the blanket of BOLL material in the outermost lattice unit and the accompanying increase in enrichment demands. On a full pile basis, this loss represents about 5%. However, on the assumption that an atom of tritium is equivalent in value to an atom of plutonium, the BOLL material in the outermost layer augments over-all pile conversion by about 4% in the green reactor, and probably more in the ripe reactor in addition to compensating the 5% loss in the E-metal blanket. An Appendix is included as …

This report discusses the critical mass control specifications for Hoods 7-C and 9-B have become obsolete due to needed storage within the confines of Hood 9-C, and equipment modifications. Nuclear safety in Hood 7-C and 9-B depends almost entirely on controlling the mass and geometry of the plutonium compounds not confined by the processing equipment. Generally, the processing vessels and associated piping are designed and arranged in the hood to be critically safe at full operating capacity. This safety is not assured, however, if plutonium masses outside of the equipment exceed certain proportions of geometry and mass. For those cases where always safe geometry confinement cannot be assured, administrative controls are established.

None

An accurate, simplified expression relating Pu conversion to exposure, was found which could be substituted for the lengthy subroutine used to calculate conversions in the Process Optimization Program.

105-KE downcomer pressure data are tabulated.

This report provides the experimental results of uranium chemical machining tests.