Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.

Report documenting the problems, design, and operation of countercurrent liquid-foam columns.

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.

The following report provides a geologic map of the Thirsty Canyon quadrangle in Nye county, Nevada.

A geologic map of the Thirsty Canyon Quadrangle, Nye County, Nevada.

From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."

Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.

From Introduction: "The primary objective of the Boiling Liquid Metal Program in the Reactor Engineering Division at Argonne is to be obtain experimental information pertinent to the the boiling-heat transfer and fluid-flow behavior of the alkali metals, especially sodium."

Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.

A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the elimination of frequently observed segmented inclusions at the seal pin interfaces.

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.

This report describes a computer program--Oak Ridge Thermal Ellipsoid Plot program (OR TEP)--for drawing crystal structure illustrations with a mechanical plotter.

Foreword: The purpose of the present work was to collect and tabulate data on fused salt mixtures.

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.

The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.

Forword: The International Symposium for Packaging and Transportation of radioactive materials held at Albuquerque, New Mexico, January 12 to 15, 1965, was a joint effort on the part of the Sandia Corporation, the Albuquerque Operations Office, and the Headquarters, U.S. Atomic Energy Commission.

From Introduction: "In this work, a forced-circulation air-water loop was employed for investigating the behavior of void perturbations. Upon attaining steady-state conditions, disturbances in the void fraction were superimposed at very low frequencies (~0.4 cps). A better understanding of hydrodynamic transient behavior will generate more confidence in the design of boiling-water reactor systems."

Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.

From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.

Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.

Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.

A report on stratospheric air concentrations of plutonium isotopes.

Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.

Introduction: The objective of the study was to estimate the worldwide distribution of a few broad categories of naturally occurring materials found on the land surface of the earth.