Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.

Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.

Report concerning the behavior of atoms dislodged from their positions in solid constituents by neutrons during the transition from high energy to thermal energy.

Installation of a chemical research laboratory.

Air filter and rainwater collections of atmospheric fall-out were made at Atlanta, Georgia; Urbana, Illinois; Topeka, Kansas; Fort Worth, Texas; and Nashville, Tennessee. Collections reflect the effects of the radioactive cloud from the Nevada tests.

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

APPR-1 is described and the various hazards are reviewed.

The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.

From abstract: "The design of a scintillation counter for measuring radioactive contamination of hands and feet is described."

From abstract: "An apparatus is described which automatically separates a flow of drops into a series of equal samples."

From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."

From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."

Report regarding the mathematical analysis of the exponential pile experiment using highly absorbent slugs and assuming the emitting of fast neutrons. Related theory and equations are discussed.

Summary: The Bulk Grain Irradiator will be capable of delivering gamma radiation doses in the dis-infestation range (approximately 25,000 rads) to handle 5,000 lb/hr of grain at this dose.

Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.

From introduction: The Monument No. 2 mine is in the Navajo Indian Reservation, Apache County, Arizona, about 20 miles southwest from the San Juan River at Mexican Hat, Utah, and 26 miles southwest from Mexican Water, Arizona. The property has been operated, since its discovery, by Vanadium Corporation of America, which holds a 10-year mining lease, granted through the Interior Department, to 43 acres of ground. History of the discovery of the deposit is vague, but reportedly it was first seen around 1942 by a Navajo who mentioned the occurrence to Harry Goulding, Indian trader, who in turn advised D. W. Viles of Vanadium Corporation of America. Minor portions of the deposit are held by Cato Sells and Harvey Black, Navajos, under mining permits issued by the Navajo Tribal Council. The Sells acreage is being operated by Climax Uranium Corporation.

Abstract: The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Tonopah National Topographic Map NJll-5 is presented in Volume I and II of this report. The airborne data gathered is reduced by ground computer facilities to yield profile plots of the basic uranium, thorium and potassium equivalent gamma radiation intensities, ratios of these intensities, aircraft altitude above the earth's surface, total gamma ray and earth's magnetic field intensity, correlated as a function of geologic units. The distribution of data within each geologic unit, for all surveyed map lines and tie lines, has been calculated and is included. Two sets of profiled data for each line are included with one set displaying the above-cited data. The second set includes only flight line magnetic field, temperature, pressure, altitude data plus magnetic field data as measured at a base station. A general description of the area, including descriptions of the various geologic units and the corresponding airborne data, is included also.

Data listings from the area surveyed in a report on the Hot Springs containing averaged record data listings.

Data listings from the area surveyed in a report on the Hot Springs including single record reduced listings.

Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.

Abstract: The thermal distortion of a Y-shaped hafnium control rod heated by arrays of individually controlled radiation heaters was studied. The large axial and radial temperature gradients specified for this control rod were easily obtained with the radiation-heating method. The distortion, as measured with dial indicators, amounted to a 2-mil movement of the free end of the rod in the direction of the coolest blade.

Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.