Abstract: "Some discussion is given of the possible real and charge parity degeneracies of K mesons. An explicit model is used to illustrate the superselection rule, which forbids the K meson to be a mixture of intrinsic parity states and at the same time conserve parity in decay. The discussion is extended to charge parity; the 01, 02 scheme appears to be more than an exercise in polarization phenomenons and to involve a radically new basic assumption--namely, that the 0-0 and 0-(-0) are degenerate states. The [tau]-0 is compared with the 02 as a long-lived K meson, and a method of experimental distinction is described."

Abstract: And investigation of the interactions between 300-Mev neutrons and xenon was made by means of a cloud chamber in a pulsed magnetic field of 21,700 gauss placed in the neutron beam of the 184-inch Berkeley cyclotron. Eighty-seven negative pion events and 257 other stars were analyzed. In addition an experimental check was made on the energy of the incoming neutrons. Classification, identification, and angular and energy distributions of prongs associated with all events are presented. Interpretations of results are given.

The following report discusses a method used to solve a two-end-point problem for second-order differential equations. The point of the method is to keep the two-end-points in the same order of magnitude.

Report discussing the properties of a plasma held in a steady state by a magnetic field. Properties such as "electric and magnetic fields, current density, particle density, and macroscopic velocity" are determined analytically by assuming uniform temperature throughout the plasma.

This report follows experiments concerned with a particular proposal or set of related proposals of means for the production of plasma with density above 10-11 particles per cm-3 with a temperature of the order of a few electron volts.

Report discussing a plasma containment configuration which appears to have no escape cone. From abstract: "Arguments are given to show how the containment process works, including experimental evidence deduced from published reports on "electromagnetic levitation."

Summary: By controlling certain elements within a vacuum chamber from an external station, a charged particle experiment is performed without opening the chamber, thereby saving considerable time and labor. By pre-programming the experimental sequence on the external controls, the experiment can be performed from beginning to end with a minimum of operator attention. The data collected can be read out automatically on a punched paper tape for subsequent transmission to a digital computer.

The heat generated by reactor fuel elements create thermal gradiants which cause thermal stresses of considerable magnitude. An elastic solution for these thermal stresses can be calculated with the equations given in Timoshenko's and Goodier's book (1) on elasticity if the fuel element is assumed infinite in length. An exact elastic solution for a finite cylindrical fuel element is given in this report in order to evaluate the effects of fuel element length on the thermal stresses and the effects of having the free end material distorting the end closure.

The Redox solvent extraction process for the separation of uranium and plutonium from their fission products and from each other has operated on an over-all basis very successfully for more than four and one-half years. During this time, there have been occasional periods of high product losses and/or poor separation of fission products from uranium or plutonium as well as periods of poor operability due, among other things, to emulsification and entrainment. The search for the cause of these various process troubles has resulted in almost continuous testing of the process solvent in attempting to determine its contribution, if any, to these difficulties. This report documents the history of the Redox Plant solvent.

Summary: The justification of using polyethylene whose hydrogen density of 0.132 gm/cm³ with a distributed void of 15.9 percent as a mockup of water at 70°F and having a hydrogen density of 0.111 gm/cm³ was tested in the FCE. A mockup close to the BORAX core was built and its critical mass determined. Corrections were calculated for differences in the hydrogen desnity and self shielding of the fuel. The effective FCE critical mass agreed with that of the BORAX core to within one percent.

A two and one-half year period of extreme caution where titanium and nitric acid are involved has passed since the occurrence of the last and most serious uncontrolled incident involving titanium and nitric acid. During this period controlled explosions involving titanium and nitric acid have been routinely reproduced, additional laboratory and pilot plant experience has been gained and successful industrial applications have been appraised. Based on laboratory data and the known industrial experiences, it is concluded that titanium can be safely employed in systems handling nitric acid that contains more than two (2) percent water. It is recommended that the titanium heat exchanger recently fabricated by the Technical Shops be installed in the Purex Plant plutonium concentrator when replacement of the stainless steel unit now in service becomes necessary.

The object of this study was to determine the effects of several annealing treatments and aging treatments on the tensile test behavior of Zircaloy-3b.

Hydrogen peroxide has been used to reduce plutonium (VI) in nitric acid solution to the (IV) valence state. However, reduction of plutonium (VI) solutions containing iron has often been incomplete when hydrogen peroxide was used as the reducing agent. Since reduction of plutonium (VI) has been applied in plant solutions containing iron, a study of the plutonium (VI) reduction with hydrogen peroxide was undertaken. Variables tested included plutonium, nitric acid, and iron concentrations.

This document covers work done in 3- and 4-inch-diameter glass columns directed toward the development of improved cartridges for the Purex Plant final uranium cycle extraction column, the 2D column. A nozzle plate cartridge for the extraction section and a mixed plate cartridge containing both stainless steel and fluorothene sieve plates for the scrub section were developed. In 3- and 4-inch-diameter glass columns these cartridges have a uranium extraction efficiency as good as or better than the present cartridge; and a scrubbing efficiency, based on the transfer of chloride ion, about the same as the present cartridge.

A report which is about an investigation to determine the solubility of uranium in thorium.

In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the heat deposition rates due to gamma rays. Neutron fluxes in the core and reflector regions of the ART are to be obtained from two-dimensional multigroup calculations (performed by the Curtiss-Wright Corporation). These fluxes, in conjunction with the neutron absorption cross sections, determine the neutron capture and inelastic scattering rates in the core and in the reflector. The data in this report permit the calculation of the number of gamma rays originating at various energies at every point in the core and reflector.

From abstract: "A pump-mix mixer-settler was demonstrated to have an overall efficiency greater than 90 per cent for the extraction of uranyl nitrate from tributyl phosphate at total flow rates up to 45 gallons per minute. Phase separation was satisfactory at 45 gallons per minute, at which flow rate the residence time in the settlers was 1-1/2 minutes. It appeared possible that a throughput approaching 60 gallons per minute would be operable although at an over-all efficiency of less than 90 per cent. The tests were made on a three-stage unit, but the data can be extrapolated to multistage units. The effects of design of the impeller and mixing section, impeller speed, flow rates and ratios, and operating temperatures were studied. The mechanical performance and dependability of the unit were excellent."

From abstract: "A tester was developed to detect nonbonded areas between the cladding and the core of hollow slugs. These slugs are one inch in diameter and eight inches long, and have a 3/8 inch axial hole. The tester employs an ultrasonic detector previously developed at the Savannah River Laboratory. A transducer 5/16 inch in diameter was developed to pass down the inside of the slug and a mechanical feeder was constructed to provide an automatic inspection cycle."

From abstract: "A tester, utilizing eddy currents, was developed to detect inclusions and voids in aluminum cans. The sensing element is a small probe that does not touch the can under inspection. An experimental feeder, developed along with the tester, permits the automatic inspection of one can per minute."

This report is essentially a procedural account of the fabrication of certain enriched ZPR-III fuel plates for use in the ANL fast critical experiments at Arco, Idaho. A total of 208.92 kilograms of fully enrich, unalloyed uranium was processed. Of this amount 202.74 kilograms was received in the form of Oak Ridge type reduction buttons and 6.18 kilograms as pressed-powder plates. The completed fabrication consisted of 720 rectangular fuel plates having the nominal dimensions 3in. x 2in. x 1/8in. Their combined weight of 159.21 kilograms represents 76.22% of the weight of enriched material processed. The final distribution of the enriched material was as follows: [figure not transcribed].

A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.

A uranium metal critical assembly consisted of a 15 inch diameter core with an average U235 content of 16-1/4%, surrounded by a 3 inch thick natural uranium reflector. The critical mass was 692 kg of core material.

This document presents a set of machine-computed curves involving a wide range of Kb and Kc, from which both thermal and resonance values of (E-1) may be obtained.

The information in this report is based on experience with a similar unit installed on experimental pule columns in the 321 Building. These installations were made to demonstrate the feasibility of the system. In one case, the installation on the 2A Prototype Column, the differential pressure cell (D/P cell) bottom interface control system was monitored by a capacitance-type instrument. The other installations were made on glass columns and were monitored visually.