Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.

This report describes the hydrology and evaluates the water resources of the ERTS, sets these in their regional perspective, and forecasts conditions and effects during future years.

Geologic factors in the physical environment of the National Reactor Testing Station control the amount and availability of the water supply, the methods and efficiency of obtaining water, and the behavior of waste materials that are disposed on the ground or beneath the land surface.

From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.

Central subject is the ground-water geology and hydrology of the National Reactor Testing Station, with special reference to problems of water supply, water use, and waste disposal, and to the relation of these to water supply and use on the Snake River Plain.

From abstract: "Detail and engineering drawings for the Engineering Test Reactor."

Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).

Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).

Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).

Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).

Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).

Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).

Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.

Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).

Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).

From introduction: "This report describes the selected site for a prototype nuclear plant, the reactor safety aspects for the site, the modified design of the plant, and estimate of the design and construction cost."

Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.

Report regarding the installation and testing of a neutron crystal spectrometer. This was part of a slide show presentation.

Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).

Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.

Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.

Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).