The object of this test is to determine the hydraulic characteristics of the proposed overbore process tube assembly designs which are to be installed on 105-C reactor for the 40 tube overbore fuel element test.

From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.

From abstract: "The dissociation of acids in tertiary butyl alcohol has been studied by potentiometric, spectrophotometric, and conductimetric methods. Values for the over-all dissociation of perchloric and picric acids and several tetrabutylammonium salts were estimated by the Fuoss-Kraus treatment of conductance data. Potentiometric studies were carried out at constant ionic strength in order to minimize activity coefficient variations. An acidity scale was established from potentiometric measurements at a glass electrode, and conductance values of dissociation constants. A method was developed for the evaluation of the over-all dissociation constant of weak acids using potentiometric data for hydrogen ion activities and conductance data for the corresponding anion activities. Over-all dissociation constants are reported for perchloric acid, picric acid, 2,4-dinitrophenol, and benzoic acid. Apparent dissociation constants from potentiometric measurements at a constant ionic strength were determined for hydrobromic, nitric, hydrochloric, picric, and p-toluenesulfonic acids."

This is one of twenty-one volumes summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume summarizes the methods and techquies developed for use in the thermal design of nuclear reactors associated with that program.

Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.

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From Abstract: "The electric field is plotted and its construction steps for axial symmetry are given."

Introduction. High voltage silicon mass transistors have the ability to perform circuit functions similar to the gas thyratron tube. Upon being triggered the transistor junction breaks down, or "avalanches", and can conduct a large current for a short time. The rise time of the avalanche breakdown pulse can be short, and the delay between triggering and avalanching can be short and very consistent. This avalanche action is non-destructive if the amount of peak and average power being dissipated at the junction is limited by the circuitry.

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Report presenting more than 500 references to the field of temperature measurement. These references were collected from two general sources: Scientific and technical literature and government reports. The period covered is from 1953 to June 1960, with some from earlier dates. References are divided into a number of categories based on the type of instrument used. Some references to calibration of instruments and to scientific theories upon which temperature measurement is based are also presented.

Abstract: "Fifteen in situ interval densities were calculated from the borehole gravity meter observations made in Test Well-B. The weighted average density for all the rocks sampled by the gravity meter is 1.83 gm/cc. The alluvium density ranges from 1.71 to 1.82 gm/cc and averages 1.76 gm/cc. The lake beds range from 1.91 to 1.93 gm/cc and average 1.92 gm/cc. The Rainier Mesa Member averages 1.83 gm/cc. The Tiva Canyon Member averages 1.74 gm/cc and the upper 110 feet of Topopah Spring Member has a density of 2.30 gm/cc."

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.

It is necessary to provide the option of using either aluminum or zirconium tubes in the C pile 20-tube overbore test. A bumper-type fuel element has been designed to fit a fixed ribbed aluminum tube size; zirconium tube dimensions were then determined which will provide the same flow and pressure drop when the fuel element is changed from bumper type or self-supported without changing other fuel dimensions.

Fuel element swelling problems have been experienced in the high-exposure fuel irradiation program in C Reactor, In an effort to determine the mechanism responsible for this swelling, three elements from C Reactor, one of which was a ruptures, were sent to the Radiometallurgy Laboratory for visual and metallographic examination. Because the swelled fuel was not numbered as to column position, the exact position of the examined elements is not known but they were believed to have come from the center of the charge and therefore exposures for these individual elements will be 25--50% higher than the column average exposures. This percentage figure was determined from data from nine tubes of C2N fuel which exhibited swelling. These nine tubes operated under nearly the same conditions as the examined elements. Maximum core temperatures for the examined elements are believed to be between 300--340C. The mechanisms for swelling were different in the high and low-exposure fuels. The high-exposure fuel exhibited grain-boundary tearing along a wide circumferential band over the entire transverse section of the fuel examined. The areas near the OD and ID were relatively free from tearing. The low-exposure fuel showed no grain boundary tearing but it did contain angular voids in …

From abstract: "The divalent metal ions of calcium, magnesium, nickel, and strontium are eluted from a cation exchange column with 1.5M nitric acid and separated from trivalent rare earths, aluminum and yttrium. Prior sequential elution of other metal ions with hydrochloric acid in acetone-water or with dilute hydrofluoric acid does not interfere with the present separation method."

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The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.

Parameters determined by a least-squares method for the reduced Simon equation and for a new, empirical melting equation.

This report is about the pay raise of Members of Congress, members of the Federal judiciary, and top-level officials of the executive branch.

A program has been carried on at Hanford for a number of years to study the effect of neutron radiation on the dimensional changes in graphite. This program has been concerned with the changes measured on small graphite samples which have been exposed to various conditions of temperature and neutron flux. Theoretical studies have also been conducted to determine damage mechanisms. The prime purpose of this research program has been to develop, with the support of the carbon companies a radiation resistant graphite for use as a reactor moderator at high temperatures. In recent years it has been found that graphite contracts under prolonged neutron exposure at temperatures above approximately 300{degrees}C. This contraction is of concern because of the possible effects on reactor operation and life. For example, distortion of process tubes, vertical safety rods, and horizontal control rod channels can cause increased operating and maintenance problems. This report presents information on the actual depression of the graphite moderator at B, D, F, H, DR, and C Reactors.

This document provides data collected by the Controlled Temperature Tensile Capsule (TISR-243).

This report consists of the conventions and campaign of 1968.

The conclusions are: (1) The formation of powder or ``oxide`` in the storage container is caused almost entirely by packaging of plutonium in plastic materials. (2) The corrosion of the plutonium follows degradation of the plastic due to the intense radiation. (3) The powder, formed by this corrosion is not PuO{sub 2} but a mixture of oxides, hydrides, and chlorides in varying proportions, depending on the type and amount of plastic in the individual storage container. (4) The powder consists predominantly of hydrides. Hydrogen is considered the major cause of severe corrosion. The surface-disruptive nature of hydriding prevents formation of any protective film on the metal. Fresh surface is provided continuously for further attack. (5) The hydrides are pyrophoric. Spontaneous ignition of the powder and metal occurs occasionally, immediately following opening of the container. This effect may be more severe for ingots than for buttons because of unreacted- or only partially-reacted metal fines in the powder from ingots. (6) Metal loss of eight percent in 100 days of storage has been observed for unalloyed ingot metal of moderate purity under the storage conditions described in this report. Corrosion rate depends on purity of the metal. Impurities in unalloyed metal inhibit …

Intelligence report compiled by the Dallas Police Department Criminal Intelligence Section on Sergio Arcacha (Smith) including a "Bill of Particulars" from his attorneys, affadavits, polygraph transcriptions, and photocopies of relevant articles.