From introduction: This volume presents the results of a conceptual design study for an intermediate size, 75 megawatt power plant utilizing an organic moderated and cooled reactor.

From summary: This report summarizes the work performed in a brief study made for the AEC of boiling water reactor power plants in the 5 to 40 eMW output range.

From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.

From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.

"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."

From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.

From introduction: This section presents the principal results of the optimization study done to establish the economic basis for selection of the core and fuel design.

From introduction: The objectives of this study are to determine the estimated capital and energy costs of this typical conventional coal-fired installation, consistent with a schedule calling for completion of construction April 1964.

From summary and conclusions: The purpose of this volume is to present the results of design studies to select the optimum-sized electric power station utilizing an organic cooled nuclear reactor and to evaluate and optimize the various reactor concepts, with special attention to selection of the moderator, consistent with the basic design criteria established by the AEC.

From preface: This report was prepared by a task force that met continuously in January and February of 1959 for the purposes of making a relative comparison of the fluid fuel reactor concepts for technical feasibility.

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.

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.

Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.

From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.

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).

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).

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.

"The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).

Report regarding thousands of hours of testing Chromel P-Alumel thermocouple material with MgO insulation.

Report describing a computing device called the Four-Linear-Element Package Analog Computer (FLEPAC) at the Oak Ridge National Laboratory. The report includes a description of FLEPAC as well as instructions for its use.