In an experimental program recently completed at the 184-inch synchrocyclotron in Berkeley, data were obtained on elastic {pi}{sup +}-p scattering at a laboratory energy of 310 Mev. Quantities measured were the differential cross section, the total cross section, and the polarization of the recoil protons as a function of center-of-mass angle. We have analyzed the data in terms of S, P, and D waves and have obtained only one acceptable solution. The resultant set of phase shifts is of the Fermi type. The D-wave phase shifts are small but definitely needed to obtain an adequate fit to the data. Owing to the relatively high accuracy of the cross-section data and the inclusion of the results of the polarization experiment, the errors on the small phase shifts have been reduced to less than 1{sup 0}. The differential cross-section and polarization data are given in Tables I and II.

During the course of process engineering work at the K Reactors, a wide variety of problems have been encountered where hydraulic information was required. This information was, obtained from various documents, from calcuations, and from actual tests run specifically to obtain the information. In order to simplify work of this nature in the future and to present a convenient means of obtaining information, the data so collected are summarized and graphed in this document.

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This monthly document details activities of the Hanford Operations Office during the month of October 1959. (FI)

The reactivity accounting and calculating techniques currently used in operational physics work are almost entirely based upon the flux squared weighting theorem. This theorem has some very serious limitations as the flattening of the reactors is increased. As a consequence many of the calculating techniques and results are theoretically unsound. Unexplainable discrepancies from pile to pile, and in reactivity data compared to original startup data and lattice physics measurements have been noted in the past. This report describes a method of reactivity evaluation based upon a one-group diffusion theory and a multi-region cylindrical geometry approximation. Results are presented which indicate that the methods outlined provide satisfactory accuracy. It is recommended that the methods outlined be adopted for routine reactivity evaluations as soon as the necessary machine computations have been made and standard procedures have been developed. Specific recommendations and results will be published as supplements to this report as soon as data are available.

Following-the K-pile start-ups in early 1955, a program of planned power raises was begun. The operating level had reached 1700--2000 MW by late 1955, and a severe operational control problem became apparent; the power distribution in the reactor was difficult to control and appeared inherently unstable. A study of available data led to the initiation of a production test so that a more detailed study of the phenomena could be made. This report describes the measures taken which led to an improvement in the operating characteristics of the K-piles; the current status and future outlook are also discussed in a general way.

This document details activities of the Fuels Preparation Department during the month of February 1959. (FI)

A resume of Health Physics activities for April, May, and June, 1959 is presented. Discussions and tabulations which summarize results of field surveys, biooassy, personnel monitoring, and environmental surveys are included. The thorium redrumming program reactivated for the summer. Work is in progress to move th "HH" Building process to the "T" Building. The ventilation system for the Hot Gas Facility was extended to handle the ventilation requirements for tthe R-108 Surveillance facility. "Hot" work in R-108 began in June. During this quarter "hot" work was initiated in the new Plutonium Alloy Research facility. Health Physics design criteria for the proposed Clover facility has been submitted to the Engineeering Department. The installation of the air monitoring systems in the new Cryogenics facility and iin the new Ceramics facility is essentially complete. We have embarked on the program of converting all of our personnel monitoring and survey record keeping systems to the IBM system.

S>Portions of two samples of HRT fael solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined. The values found, 325 er inch per 1 C for one sample and 326 er inch per 1/2 C for the other, are slightly lower than predicted from experiments with synthetic fuel solutions (329--330 C) but the discrepancies are small enough so that they could be accounted for by the minor differences in composition between the synthetic and reactor fuel solutions. There appears to be little reason to believe that the high radiation level which the fuel- solution is exposed to in the reactor has a significant effect on its phase behavior, at least after it has cooled to 2r per ml. Dilution of fuel solution wvith 8 vol.% of 30% H/sub 2/O/sub 2/ and with the same amount of H/sub 2/O increased the two-liquid phase formation temperature about 2 EC but increasing the free D/sub 2/SO/sub 2/ concentration from about 0.017 to 0.04 M raised the immiscibility temperature 19 to 345 C. (auth)

This paper was previously abstracted irom the original language and appears in NSA Vol. 11, as abstract No. 13429. l9565 Selection rules, which occur ln the annihilation of a found nueleon-antinucleon system were examined. The decay of neutral K mesons with allowance for the conservation of combined parity was also investigated. (auth)

Tables of numerical values of all necessary functions and instructions on their use in the stress analysis of circular plates which have a linear thickness-radius relationship, and which are loaded axisymmetrically, are presented. The analysis is based on the classical smalldeflection theory. Emphasis is placed on plates whose thickness at the inner radius is greater than the thickness at the outer radius. However, a limited number of plates for which the opposite is true may also be analyzed by the procedure presented. The limitations on the dimensions of the latter type of plate are explained. (auth)

Analytical programs have been described for uranium recovery processes for aluminum-uranium and zirconiumuranium reactor fuel elements. It is the purpose of this paper to describe the analytical program for the uranium recovery process involving stainless steel-uranium reactor fuel elements. The recovery process consists of a two step dissolution and the regular liquid-liquid solvent extraction using TBP in kerosene. Sulfuric acid is used to dissolve the stainless steel. As a result of the sulfuric acid dissolution the uranium is converted to a slurry. The uranium slurry is then dlssolved in nitric acid. After the nitric acid dissolution the feed material is compatible with the extraction columns used at the Idaho Chemical Processing Plant for other type fuel elements previously described. In order to analyze samples of dissolver solutions for constituents necessary for plant operation, three new analytical methods were developed. These methods are a rapid method for determining uranium, one for nitrate and one for sulfate. Methods are described for urarium, acidity, specific gravity, nitrate, and sulfate in the dissolver solution; also for small amounts of uranium in the extraction column raffinates. Samples of dissolver solution and first cycle aqueous raffinate contain large amounts of fission products. These samples require shielded …

Helicity amplitudes are written for photoproduction of mesons and related in the amplitudes of Chew, Goldberger, Low, and Nambu. The expansions of both types of amplitudes in terms of amplitudes for particular angularmomentum states are then inverted. (auth)

A 48-in.-long liquid-hydrogen target is described. The operating characteristics of the target and its safety features which follow the regulations laid down by the Hydrogen Safety Committee of the Lawrence Radiation Laboratory are stressed. (auth)

Using a special reactive form of high-purity alumina, claddings were applied to UO/sub 2/ particles by a tumbling technique. The clad pellets were isostatically pressed at 100,000 psi and then sintered at 2800 deg F in hydrogen. crack-free spheroidal pellets ranging from 1000 to 2000 mu in diameter were produced. The dense Al/sub 2/O/sub 3/ envelopes surrounding the UO/sub 2/ particles were estimated to be 300 to 500 mu thick. The Al/sub 2/O/sub 3/ claddings protected the UO/sub 2/ from oxidation when the pellets were heated in air for 100 hr at 1200 or 1800 deg . There was no measurable release of fission products from irradiated clad particles heat treated at 1700 deg F in vacuum for 7 days after exposure to 6.0 x 10/sup 12/ nv for 1 hr at room temperature. Claddings of other oxides, such as Beo or MgO, probably could be applied by the same techniques used in applying the Al/sub 2/O/sub 3/ claddings. (auth)

This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work.

An investigation was conducted to determine the feasibility of using an NaK free-convection-cooled shaft freeze seal on the SRE main sodium pumps. The use of sodium in this application instead of tetralin eliminates the carburization hazard present should the seal coolant-(tetralin) leak into the sodium system. Results and recommendations are included. (J.R.D.)

The temperature coefficient of reactivity at the plant operating temperature was --1.92 DELTA K/ DELTA T x 10/sup -//sup 4/, as obtained from the curve of the temperature coefficient plotted as a function of the temperature. (B.O.G.)

Based on the results of detailed fabrication studies, an evaluation of the effects of varying the type and size of UO/sub 2/ particles, the type and size of stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures, and atmospheres, roll-clading temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures was made for UO/sub 2/stainless steel dispersion fuel elements. Transverse tensile tests, creep-rupture tests, metallographic examination, radiography, density measurements, and x-raydiffraction studies were used to evaluate the structure and properties of the fuel elements. From these studies a reference fabrication procedure for GCRE fuel elements was established. The fuel element core contains minus 100 plus 200-mesh hydrothermal UO/sub 2/ dispersed in an 18-14-2.5 alloy matrix prepared from minus 325-mesh elemental iron, chromium, nickel, and molybdenum powders. Commercial Type 318 stainless steel is used for cladding. Core compacts are sintered in steps to 2300 deg F after cold compacting at 15 tsi. Evacuated picture-frame packs are hot rolled from a hydrogen muffle at 2200 deg F with a 40% reduction in thickness on the first pass and a 20% reduction in thickness on remaining passes. After annealing at 2300 deg F, the fuel elements are given a …

Experimental data regarding the biologic consequences of exposure to several environmental variations associated with actual and simulated explosive detonations were reviewed. Blast biology is discussed relative to primary, secondary, tentiary, and miscellaneous blast effects as those attributable, respectively, to variations in environmental pressure, trauma from blast-produced missiles (both penetrating and nonpenetrating), the consequences of physical displacement of biological targets by blast-produced winds, and hazards due to ground shock, dust, and thermal phenomena not caused by thermal radiation per se. Primary blast effects were considered, noting physical-biophysical factors contributing to the observed pathophysiology. A simple hydrostatic model was utilized diagrammatically in pointing out possible etiologic mechanisms. The gross biologic response to single. "fast"-rising overpressures were described as was the tolerance of mice, rats, guinea pigs. and rabbits to "long"-duration pressure pulses rising "rapidly" in single and double steps. Data regarding biological response to "slowly" rising over-pressures of "long" duration are discussed. Attention was called to the similarities under certain circumstances between thoracic trauma from nonpenetrating missiles and that noted from air blast. The association between air emboli, increase in lung weight (hemorrhage and edema), and mortality was discussed. Data relevant to the clinical symptoms and therapy of blast injury are presented. …

Progress is reported in the development of scavenging systems for the collection of fall-out. Data are included from tests of two cyclone separators for the collection of air samples. Results are included from laboratory studies on the scavenging of aerosol particles by evaporating and condensing water droplets. (C.H.)

Equipment and techniques for high-pressure high temperature solid-state studies were developed, and some preliminary results for the reaction of uranium oxides with other oxidcs were obtaincd. A new die design was evolved which appears suitable for any work currently contemplated. The maximum capabilities of this new die are as yet undetermined, but its theoretical pressure limit is in excess of 200,000 atm. The die differs from similar equipment in that internal heating of the sample is employed and maximum pressure and temperature can be maintained simultaneously. Most of the preliminary work on materials synthesis was performed at pressures up to 40,000 atm. and temperatures to 1000 deg C. No reactions were found in the system UO/sub 2/ and U/sub 3/O/sub 8/ with BeO while under pressure. However, a reaction between Sc/sub 2/O/sub 3/ was detected which was not detected at normal pressure. Sc/sub 2/O/sub 3/ reacted with U/sub 3/O/ sub 8/ under pressure as it does at ambient pressure. A new high-pressure high- temperature phase of U/sub 3/O/sub 8/ was produced. Preliminary study of the U/ sub 3/O/sub 8/ pressuretemperature phase diagram was made. The crystal structure of the new U/ sub 3/O/sub 8/ phase has not yet been determined. …