From purpose and scope: The Justice Department and the AEC embarked upon this joint study so as to provide the basis for preparation and consideration of guidelines for the nuclear industry best designed to foster vigorous growth and to provide a sound basis for government action.

Introduction: This report describes a program to develop a nondestructive (ultrasonic) tester and testing procedure to perform integrity tests on isotope heat source containers. The increased application of isotope heat sources has brought more attention to the engineering problems encountered during fabrication. One of the most important of these problems is insuring the isotope containment during the long unattended periods of use. To determine the integrity of the heat source container, a nondestructive testing procedure must be adopted to test each heat source after fabrication.

A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review

Abstract: "A continuous countercurrent solvent extraction process utilizing dibutyl carbitol as the extractant has been developed for separating 210Po from large amounts of associated bismuth. Both laboratory and pilot plant data demonstrate the process is a suitable headend step in recovery of kilogram quantities of 210Po. Typically, the extraction process recovers over 98% of the 210Po, essentially free from bismuth (Bi DF>1500), in a dilute HNO3 solution suitable as a starting material for final concentration and purification steps."

This report follows a study that was made to develop comparative fuel cycle costs for nitride and carbide fuels in a 1000 MWe sodium-cooled fast-breeder reactor.

Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.

Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.

A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12

The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.