"This is a selected bibliography of books, journal articles and reports published on creep and relaxation in metals and ceramics from 1950 to March 1959. Particular attention has been paid to studies on or applicable to the consideration of creep and relaxation in beryllium oxide. Emphasis has alro been placed on studies of phenomenological materials behavior and high temperature studies."

Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.

Wind tunnel testing of swept wing fighter aircraft model for determining drag and static longitudinal and lateral stability and control characteristics. Results regarding performance, longitudinal stability, lateral stability, and strakes are provided.

Electrical resistivity data for metals which are likely to be resistance heated in heat-transfer tests were compiled and are given as a function of temperature. (auth)

This document details activities of the Hanford Laboratories Operation during the month of March 1959. (FI)

This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.

An analysis was made of the fission-gas-release incident during the pressure pumpdown of the AE-6 Reactor resulting in the contamination of the reactor room and members of the operating staff. Descriptions are given of the normal core pumping procedures, procedural alterations during the incident, the discovery of the contamination and its possible causes, and the remedial actions taken. Steps taken to minimize the chance of the occurrence of the contamination in the future are listed. (B.O.G.)

disintegrating a corrosion scale from stainless steel systems without attacking the stainless steel. In this investigation particular sample of stainless steel corrosion scale appeared to be disintegrated most effectively in a solution of the trisodium salt of N-hydroxyethylethylenediaminetriacetic acid (Versenol) and ammonium acetate. In a subsequent test with this solution in a REED dynamic Ioop a considerable disintegration of scale from the loop was observed. in this test after a period of approximately 60 hours, the iron content in the solution was found to be 10 g per liter; thus indicating that the mixture of Versenol and ammonium acetate can be used to disintegrate partially the corrosion scale from a stainless steel system. (auth)

A series of tests conducted in an attempt to reduce the observed O2 content of primary recirculation loop water to a value of <0.14ppm by the current loop method which is a combination of pressurizer degasification and venting flow.

The thermal expansions of commercial uranium dioxide specimens were measured up to the melting point. The linear expansion of dense, normal grain size UO/sub 2/ follows closely the equationi L = L/sub 0/(1 + 6.0 x 10/sup -6/t + 2.0 x 10/sup -9/t/sup 1.7 x 10/sup -12/t/sup 3/). An anomalous expansion was noted in the temperature range 1000 to 1500 deg C. Above 2500 deg C the rapid vaporization and crystal growth of UO/sub 2/ necessitate the application of heating techniques which provide rapid heating and quenching in order to obtain reliable data. The use of solar and arcmelting furnaces for this type of measurement is described. (auth)

The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.

The energy and angular distributions of the gamma rays leaking from the BSF reactor were computed by (((((((((Abstract unscannable))))))))))

The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much of the planned hot-cell inspection was postponed and complete examination of all but a few specimens was indefinitely suspended. The few examinations that were completed are described in this report, along with a description of the disassembly of the ARE system. Diagrams of the fuel system, sodium system, and off-gas system are presented in Figs. 1, 2, and 3 for reference use in visualizing the disassembly process.

Report presenting the effects at Mach number 2.01 of various changes in nose and afterbody shape on the static aerodynamic characteristics of a body of revolution with a fineness ratio of 11 with an ogive nose, a cylindrical center section, and a boattail or cylindrical afterbody. Some body conditions were tested in combination with a vertical tail. Results regarding the effects of nose and afterbody modifications and vertical tail-on configurations are provided.

Report presenting an investigation to determine the effects on performance of positioning normal shocks in or upstream of both a long and a short subsonic annular diffuser. Results regarding the entrance flow conditions, performance for subsonic-entrance flows, and performance with choked- and supersonic-entrance flows are provided.

The advantages, disadvantages, and cost of constructing a auclear power reactor underground are outlinedData on underground construction of hydroelectric plants, other structures, and underground reactor projects in Norway and Sweden are reviewed. A hypothetical underground Experimental Boiling Water Reactor design and sketch are given with cost estimates(T.R.H.)

Engineering study on underground construction of nuclear power reactors.

Report presenting results for a canard bomber-type configuration designed for supersonic cruise flight at Mach numbers 2.50 and 2.87 and over a range of angles of attack and angles of sideslip. Results regarding longitudinal characteristics and lateral stability are provided. The original configuration was directionally unstable at low angles of attack, but satisfactory directional stability could be obtained using upper-surface vertical fins.

This document details activities of the Fuels Preparation Department during the month of March 1958.

This is the monthly report for the Hanford Laboratories Operation, March, 1958. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

By means of 2-group, 3-region calculations the following features are investigated for a flux-trap reactor: finite fuel-layer thickness, moderation in the fuel layer, diffusion constant of the fuel layer, reflector thickness, and flux-trap radius. A 31-group calculation was used to study simultaneously finite fuel-layer thickness, moderation in the fuel layer, and epithermal absorptions as and fissions. The results obtained are very near those obtained for the idealized case in ORNL CF-58-1-4. (auth)

and HT-22 are described. These runs were made to determine the handling characteristics of a slurry containing thoria calcined at 1600 deg C and to evaluate the operation of the 5-gpm slurry pump. The experimental procedures are described. It was concluded that 1600 deg C calcined 0.7 mu mean particle size thoria can be satisfactorily circulated using the 5-gpm pump. (J.R.D.)

Maximum HRT dome wall temperatures for reactor powers up to 10 Mw were calculated for both an insulated amd uninsulated dome. Temperatures exceeding 315 deg C in the fuel solution flowing through the HRT dome section can cause phase separation which results in excessive corrosion rates. The results, based on very conservative assumptions, inticated wall temperatures exceeding 315 deg C could occur in the insulated dome when operating the reactor at 10 Mw. Using the same conservative assumptions, the analysis of the uninsulated dome indicated wall and bellows temperatures below 300 deg C. (auth)

A wind-tunnel investigation to determine the effects of both single and twin jets on base drag of a cylindrical body has been conducted at Mach numbers from 0.6 to 1.4. The plane of the jet exit was varied with respect to that of the afterbody. Jet total-pressure ratio ranged up to 20. Significant improvements in base drag were obtained by extending the plane of the jet exits beyond the afterbody base and by venting the base cavity to the external stream.