The following document describes suggestions on the application of the A-48 ion accelerator beam currents to the Sherwood Program.

A simple method of solving for the phase shifts of the pion-proton scattering is presented. The rapid solution afforded can be utilized, as the Ashkin diagrams have been employed, to give starting values to an electronic computer or alternatively to analyze with more ease the variation of the phase shifts as a function of the input data in terms of the coefficients of the angular distributions. A new plot of a function of the total cross section versus the pion energy is introduced. The nearly straight line resulting should help to evaluate the experimental data.

Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after irradiation and after decay of the protactinium 233 was greater than before irradiation. A fuel element of this nature appears to offer excellent potentialities from the standpoint of radiation stability.

This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.

Results of eight runs using in-line U photometers in organic and aqueous streams of the Purex Hot Semi-Works are presented. Their operation, both mechanically and electrically, was satisfactory, indicating changes in stream U concentrations over wide ranges.

Flowsheet considerations and information developed for the large (size 2) Purex pulse generator⁽¹⁾ indicated the need for information on the operating characteristics of the small (size 1) Purex pulse generator.

The effect of prolonged heating of cold worked Ziracloy-2 at a temperature of 360°C on the mechanical properties of the material was investigated.

In discussion with a number of people at HAPO, KAPL and ANL a hypothesis has been evolved which appears to fit available information concerning irradiation embrittlement of uranium as well as indicate a possible solution to the problem. The purpose of this memorandum is to expound the hypothesis as an aid to those working with the problem. Since it imbodies the ideas of many people, no claim to unique authorship is implied.

Under the general heading of Reactor Lattices are reported a new method of calculating resonance escape probabilities, results for the effective mass of a proton bound in the water molecule, and a comparison of similar techniques for calculating lattice constants developed independently by Hanford physicists and by a school of Russian physicists (as reported at the Geneva Conference). An estimate of maximum errors in f and η for thermal systems is described. Experiments and analysis thereof on the effects of neutron streaming in air channels through a moderator are reported. Buckling calculations and experimental results are given for graphite lattices employing 1.17-inch diameter natural uranium slugs and U²³⁵-Aluminum alloy slugs. An experimental measurement of the critical mass of an annular cylindrical array is described. Some measurements on, and the status of, construction of the Lattice Testing Reactor are reported. Under Instrumentation, development of a BF/sub 3/ counter suitable for operation at elevated temperatures is described. Some measurements on, and the status of, construction of the Lattice Testing Reactor are reported. Under Instrumentation, development of a BF₃ counter suitable for operation at elevated temperatures is described. A method of determining the screening parameter in the Thomas-Fermi model of the atom is …

The error that results when it is attempted to evaluate stress from a reading taken on a single element SR-4 strain gage in a biaxial stress field is discussed. A method is presented for relating SR-4 rosette strain gage readings directly to the biaxial stress state without the necessity of first converting strain gage readings to true strains. Correction formulas are presented for use when single element SR-4 gages are used as rosette elements or as stress gages.

A preliminary mathematical study is made of the maximum expected expansion of barium titanate ceramic. It is noted that there is insufficient physical evidence for a complete answer and some possible mathematical models are discussed and compared.