>The analytical procedures for wet adsorption methods for surface area measurements are described. (J.S.R.)

The May, 1956 monthly report for the Chemical Processing Department of Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished products operation, power and general maintenance, financial operation, engineering and research operations, and employee operations. (MB)

S>Tables of elementary-particle data in easily accessible form are presented for researchers in highenergy physics. Included are: The Masses used Mean Lives of the Elementary Particles; Atomic and Nuclear Properties of Materials; Particle Scattering; atomic and Nuclear Constants; and Particle Decay and Reaction Dynamics. (T.R.H.)

A three-phase linear induction pump was designed, constructed, and installed in the Sodium Reactor Experiment to control moderator temperature. A maximum flow rate of 91 gpm was obtained at 760 deg F, at 12.4 psi, and an efficiency of 1.7%. (C.J.G.)

Theories of diffusion processes in water are discussed and the dispersion of radioactivity is calculated from an interpretation of the molecular diffusion equation with modifications which tend to fit the equation to from fission products in solution are made for a number of situations of interest. Parametric solutions are obtained and plotted on graphs which may be used to obtain water concentrations and thence dose levels. (auth)

OTS. Heating and cooling tests were made on the ORR HN-1 in-pile loop mockup 0-l-20 to test the operation of the loop when subjected to reactor scrams or setbacks. The loop was fitted with additional heaters to simulate reactor heat. Reactor transients were simulated by manually changing the power at a predetermined rate. It was found that thc loop control system was adequate and that loop temperatures could be maintained within a total change of 5 deg C. (auth)

This document details activities of the irradiation processing department during the month of May 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

ABS>A list of 222 references pertaining to corrosion by molten Li and related subjects was compiled in connection with a Lithium Symposium held at the Oak Ridge National Laboratory on August 7-8, 1957. This list is by no means exhaustive but it is thought to contain most of the information presently available on these subfects. In many cases the individual references will contain additional references. (auth)

Preparation of synthetic wastes from the processing of aluminum-clad natural uranium, aluminum-enriched uranium alloy, zirconium-uranium, stainless steel-UO/sub 2/, and stainless steel-UO/sub 2/-MgO fuel elements is described. These preparations will be used in waste disposal studies. (auth)

The status of the research and development of the Yankee Power Reactor is briefly summarized. (For preceding period see YAEC-66.) (M.H.R.)

plants ln England and France. With the increasing de output of given designs and probably allow operation at higher polymer contents than orignally foreseen, thereby reducing the make-up requirements. The physical characteristics of the OMRE such as critical loading, temperature coefficient, and general stability appeared to be close to the predicted values. Radiation levels in the primary circuit area during full power operation appear to be so low that maintenance is possible during operation. The reactor has been run for a full month at 30% polymer concentration and is, at the time of this writing, brought to a still higher steady state percentage of breakdown products ln the coolant stream. No evidence whatsoever of fouling or precipitation has been observed. The reactor behaves in a routine manner in all respects and invites immediate application of the OMR principle to reactors for large scale ceniral stations. Final design on one 11.4 Mwe unit for the city of Piqua, Ohio, has now stanted. A short description is given of OMR power reactors. The use of magnetic jack mechanisms for control and safety rods provides a reactors top shield without penetrations, as well as an unpenetrated lower core vessel, still avoiding any interference …

Progress in the design and development of the Yankee Power Reactor is briefly reviewed. (For preceding period are YAEC-89.) (W.L.H.)

Progress in the design and development of the Yankee Power Reactor is briefly reviewed. (For preceding period see YAEC-79.) (T.R.H.)

The status of the various development projects associated with the Yankee Power Reactor is given. No data are reported. (For preceding period see YAEC-55.) (D.E.B.)

The status of the various development programs for the Yankee Power Reactor is outlined. No data are given (For preceding period see YAEC-70.) (W.D.M)

Work directed toward developing a stainless steel clad UO/sub 2/ fuel element is reported. Methods are being developed for utilizing chemical poisoning for reactor in the reference environment. The design and development of mechanical features of fuel assemblies, control rods, baffles, the support structure, the reactor vessel closure, and fuel handling tools are presented. (For preceding period see YAEC-101.) (W.L.H.)

The research and development required to build a 134-Mw(e) pressurized- water nuclear water power plant having a core of slightly enriched uranium dioxide fuel pellets contained in stainless steel tubes are described for Oct. l958. Corrosion testing of nickel-plated CdIn-Ag control rod alloy is described. Preliminary results from hydrostatic pressure testing of various types (For preceding period see YAEC-99.) (W.D.M.)

A brief description and the planned operating parameters of the ORNL-MTR- 44 MSPR in-pile loop are given tegether with the operating characteristics of the major components of the loop. (auth)

The ignition temperature of Mg is influenced by numerous variables of which the most important appear to be alloying (or dissimilar metal contact) and the concentration of the Mg vapor over the heated metal. Most alloying elements lower the ignition temperature; however, Re additions inhibit the pyrophoricity of alloys up to temperatures in excess of their melting point. Although there is evidence that the ignition temperature of Mg is O/sub 2/-pressure sensitive, its effects are slight in comparison to the above factors. Similarly, the changes observed in the ignition temperature resulting from changing the corrosive gas to CO/sub 2/ and SO/sub 3/ are slight. The corrosion products resulting from decomposition of these gases are MgO and C for atmospheres composed of CO/sub 2/, air, and 0/sub 2/, and MgSO/sub 4/ in the case of SO/sub 2/ atmospheres. Moisture in the above gases accelerates the corrosion rate. In CO/sub 2/, the rate is increased by moisture by a factor of 4 in one month to a factor of 2 after two months. There is no information on the effect of moisture on the ignition temperature; however, if the correlation between oxidation rates and ignition temperatures is still valid, it is expected …

In a series of 600 cutaneous burns in swine produced by radiant thermal energy at 0.5 and 5.0 sec exposure time, the relationship of thc surface appearance and the depth of damage of bare skin and subfabric burns was investigated. The fabrics used were a black and a gray sateen weighing 8 to 9 oz/ yd/sup 2/. It was found that there is no significant difference in the 1+ burns whether produced on bare skin or beneath fabric, either at 0.5 or 5.0 sec exposure. However, the 2+ subfabric burns average about 0.1 mm deeper in dermal damage than thc same grade barn of bare skin. Nevertheless, the protection afforded by fabric is found to be nearly the same whether the burns were judged by surface appearance or microscopically by depth of damage. (auth)

The purpose of this report is to present a set of standard pressure-drop curves for various fuel elements in process tubes of Hanford reactors. The flow and pressures within a process tube assembly under normal conditions are dependent to a large extent on the magnitude of the pressure drop across the fuel elements. The knowledge of this pressure drop is important in determination of existing thermal conditions within the process tubes and in predicting conditions for new fuel element designs or changes in operating conditions. The pressure-flow relations for the different Hanford fuel element-process tube assemblies have all been determined at one time or another in the 189-D Hydraulics Laboratory but the data had never been collected into a single report. Such a report is presented now in the interest of establishing a set of ``standard curves`` as determined by laboratory investigations. It must be recognized that the pressure drops of fuel elements in actual process tubes in the reactors may be slightly different than those reported here. The data presented here were obtained in new process tubes while reactor process tubes are usually either corroded or filmed, depending on their past history.

None

Protruding rocket antennas of low silhouette are examined using transmission-line concepts. The theory was developed specifically for nondissipative terminations and line sections; however, the formulas are readily generalized to include ohmic losses in the lines and terminations. Adaptive computations may be made for conductors other than circular and the theory may be used to analyze antennas of other missiles. (J.R.D.)

Thorium is readily extracted by a solution of tri-noctylphosphine oxide in cyclohexane from either acidic nitrate or chloride solutions. The maximum extraction coefficient in a nitrate medium is 380 as compared to 1300 for a chloride solution. In nitrate media the extraction coefficient is relativelv unaffected by changes in the anion concentration. In chloride media the coefficient varies directly with increasing chloride concentration, i.e., from about 0.4 in one molar chloride to the maximum in 7 to 10 molar. The acid concentration should be at least one molar. Thorium is not appreciably extracted from sulfate solutions. The extraction coefficient is of the order of 0.3. The addition of nitrate or chloride increases the coefficient sufficiently so that essentially 99% of the thorium can be extracted in a single equilibration. In perchlolate systems the extractlon is most efficient in one molar acid. The maximum (The above was unscabble material)