The following document provides figures with all information that describe the heavy water moderated chain reacting pile at Argonne National Laboratory.

From summary: "Various thermal and mechanical properties were measured for sintered tin oxide-matrix compacts which nominally were composed of 99 per cent by weight of tin oxide, SnO2, and one per cent by weight of zinc oxide ZnO...The tin oxide body might be expected to give good service under conditions of severe thermal shock and in an oxidizing atmosphere at temperatures up to 1500°F."

Report discussing progress made by the Chemistry Division (Section C-1) of the Argonne National Laboratory for the months of April, May and June, 1951. Information is divided into "Nuclear Chemistry and Radiochemistry" and "Basic Chemistry".

Report discussing the possibility of structural damage which is most likely to lead to dangerous release of radioactive materials, as well as "the effect of sudden loss to vacuum in a device such as that described in "Engineering Analysis, Mark 2 (4-28-51)."

"The purpose of this memo is to set down a derivation and numerical technique for a method that can be used for criticality calculations on bare reactors containing hydrogen together with another moderator such as BeO. The method and notation are that of G. Goertzel (NDA)-1, and D. Selengut (NEPA). In the interest of the computers, the numerical technique, associated notation, and calculation form are modeled after that currently used by the ANP Physics Group for BeO moderated reactors."

Report summarizing the progress of the gasket development program during the period from November 1949 to May 1950.

Report summarizing work done by the Ames Laboratory from April, 1951 through June, 1951 in the fields of metallurgy, chemistry, physics, and engineering.

A study was conducted on the elution behavior of curium (III), americium (III), plutonium (III), actinium (III), plutonium (IV), neptunium (IV), uranium (IV), thorium (IV), neptunium (V), plutonium (VI), uranium (VI), lanthanum (III), cerium (III), europium (III), ytterbium (III), ytterium (III), strontium (II), barium (II), radium (II), cesium (I) with 3.2 M, 6.2 M, and 12.2 M HCI solutions from Dower-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. In order to explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5g-ortibals in the actinide elements.

Energy values are generally accurate to 5%, except in the low energy region and except for He(3) and He(4) for which a non-relativistic conversion was made.

The complexing of lanthanum by various anions and weak acids was investigated by observing the light absorption of the complex formed with thenoyltrifluoracetone (TTA). This species showed the properties needed for a satisfactory specgtrophotometric method of analysis.

Most books on the subject of gas discharges describe the multiple banded structure which appears in the flow between two electrodes. This structure is actually due to the difficulty in getting electrons out of the cathode to support the discharge. These electrons are obtained by having a large enough potential drop near the cathode so that the positive ions may strike it hard enough to product secondary electrons. If one substitutes a hot cathode to produce a copious quantity of electrons, the banded structure will be radially changed. Hence the banding is not a pure property of the discharge, but is a complication brought on by the presence of electrodes.

The pressure and temperature cycles developed during the bomb reduction of uranium tetrafluoride by calcium have been determined. Data for the 250, 500, and 1000 gram scale reductions are given, and the apparatus used is described.

An active program is a present underway to develop equipment to handle liquid metals. Among the metals being studied are sodium and sodium--potassium alloy (the latter commonly referred to as NaK). In many of the systems being studied this liquid metal is pressurized by inert gas in the lines. At times it is necessary to bleed off some of this gas from the system. Although the gas is allowed to escape at a temperature at which the vapor pressure of sodium is extremely small, it has been found that excessive amounts of sodium are present in this gas stream. Either this sodium collects in the lead-off pipes from the system as a solid, threatening to block the passage in which it is found, or it passes out into the atmosphere. In order to explain the presence of such a dangerous concentration of sodium in the exit gas stream, it has been proposed that the sodium vapor present in the the system at high temperatures condenses into a mist or aerosol on cooling. This aerosol is stable and will not readily de-entrain or condense onto the surfaces over which it passes. Another possibility is that the oxygen present with the inert …