From introduction: "This report is concerned with exploratory experiments designed to studies the efficiency of a number of scavengers for zirconium and niobium adsorption and to provide preliminary information on the best conditions to employ on the most satisfactory of those scavengers studied, namely Super Filtrol FO. The data in this report include data obtained through October, 1949, and are by no means considered to be final. The investigation is currently being actively continued."

Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."

From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."

Introduction: "The tensile properties, hot hardness, impact strength; and corrosion resistance of some arc-melted, iodide zirconium alloys have been determined. The alloys investigated include binary alloys of zirconium containing zero to five per cent tin, binary alloys of zirconium containing zero to 0.14 per cent nitrogen, and ternary alloys of zirconium containing tin and nitrogen, tin and uranium, and uranium and beryllium."

Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."

Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."

Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.

From introduction: "The work covered in this report is a portion of the experimental research undertaken for the design of a uranium-containing metallic fuel rod for operation in air at 1090 C...This report deals with that phase which involved the testing and evaluation of various metals as barrier costs between uranium alloys, and low-carbon steel. The work is of a preliminary nature and is concerned more with a comparison of the various barrier metals than with the acquisition of numerical data, e.g., diffusion coefficients."

Abstract: "The possibility of fabricating a lightweight control rod from one of several high cross-section materials was investigated. The major effort was directed toward the development of a titanium-clad rod containing a composite core of 25 weight per cent Gd2O3 in a matrix of titanium. Experimentation on both subscale and full-scale control-rod cores showed that the fabricating behavior of the two was not analogous. To roll the full-scale core successfully, it was necessary to lower the oxide content to 17 weight per cent. Subscale investigations were also carried out on titanium-cadmium, titanium-lanthanum, and titanium-gadolinium alloys."

Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."

Abstract: "A possible method of cooling a liquid-fuel reactor is by spraying liquid metal through the liquid fuel, and then circulating the liquid metal through a heat exchanger. To evaluate the effectiveness of this cooling method, a few simple experiments were made with mercury sprayed through water. On the basis of the results, it was concluded that this method was intrinsically a low-power-density method, which could not find application except where a low fissionable-material inventory was the dominating requirement in a low-power reactor. Even there, it is thought that a boiling homogeneous reactor might be superior. The results are reported, in spite of their probably lack of value in the reactor program, simply to make the record complete."

Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."

Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."

Introduction: "When uranium slugs are irradiated in the Hanford piles, one of the many substances formed is U-237. It arises primarily from the reaction: U-238 (n,2n) U-237. This uranium isotope is a beta and gamma emitter with a half-life of 6.7 days. Because it is isotopic with U-238, it accompanies the uranium recovered by the Redox Process, and its concentration is, of course, not diminished by the fission-product decontamination cycles. As a consequence, the maximum total decontamination of irradiated uranium which can be achieved depends upon the quantity of U-237 present in the processed uranium."

Abstract: "Experimental evidence is given which indicates that electronic bombardment is responsible for damage and failure of insulating material subjected to intense corona attack. The experimental revolts are further supported by some theoretical considerations of the energy-time properties of corona discharges."

Abstract: "By a simple illustration it is pointed out that, conceivably, the real coupled character of the general magnetohydrodynamic equations may lead to much slower instability growth rates, if not stabilization, than predicted from the linearized set of equations."

"An investigation of the chemical effects of 1-Mev electrons on BrF3 at 25 degrees C has been carried out. Pressure measurements taken during the irradiation suggest the presence of Br2 and BrF5 as decomposition products and a fractional distillation of the irradiated liquid confirmed their presence. The extent of decomposition was determined both by fraction distillation and spectrophotometric methods. The radiation effect seemed to reach saturation when approximately 10 per cent of the BrF3 was destroyed. The exposure necessary for the decomposition products to reach a concentration of half the saturated value was calculated to be 2.7 microampere hours/cc BrF3 while the "G" value was found to be 1.5. A qualitative comparison of irradiation dosages from the Statiltron with that expected from spent fuels revealed that little decomposition of BrF3 reagent is to be expected from 1-say cooled Hanford fuel (in pile for 100 days) while in the case of 1-day cooled MTR type fuel (in pile for 12 days) a saturated effect might be realized in 1-3 hours. Since at most only 10 per cent of the BrF3 is destroyed it is concluded that BrF3, from a radiation resistance standpoint, is a suitable standpoint, is a suitable reagent for …

"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …

The following report follows a complete radiochemical analysis that has been made on the sample of first-cycle neutralized waste, as well as a gravimetric analysis made on the sludge in the sample of first-cycle waste.

Summary: "The problem of evaporation of secondary radioactive wastes resulting from waste disposal studies at Mound Laboratoy has been studied experimentally to determine the fundamental design characteristics of a plant size unit. Emphasis, of course, was on decontamination, but the factors affecting foaming and scaling also had to be investigated and evaluated. Generally speaking, the final design is a standard type of evaporator, the only unique feature being the relation of the two effects. Where critical, as affecting performance, the particular design features have been specified."

"This bibliography is a compilation of titles to unclassified reports, journal articles and conference papers written by members of the University of California Radiation Laboratory, Livermore and Berkeley, relating to Project Sherwood (Controlled Thermonuclear Reactions) from 1953 through 1957."

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.

Introduction:"A corrosion test program to determine the effect TBP process streams, which contain chlorides, have upon the corrosion resistance of several construction materials, was completed. Data are presented on the performance of Carpenter 20, T-309SCb, T-347. T-316 and tantalum in the RAF and RAW process streams and on the performance of titanium and zirconium in the RAW stream."

This report provides data on production test 105-329-P and solid graphite samples used to analyze damage obtained from controlled natural erosion tests. The data provided will help establish current ideas on the status of filler block graphite and interpretation of the data will assist in establishing pile operating temperature limits based on stored energy.