From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."

BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.

The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.

Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.

This document presents the results of investigations concerned with the conceptual design of a 300 KWe "Capsule" nuclear power plant.

A program of free-surface steam-water separation at 600 psig was carried out in support of the design for operation of the Experimental Boiling Water Reactor at 100 MW thermal. Reduced test data are presented without evaluation since the ANL technical representative received an original copy of the data for evaluation with respect to the EBWR design.

The Fuel Cycle Development Program is a basic development program of boiling and other water reactor technology. This is the first report to the U.S. Atomic Energy Commission of activities carried out under this program. It constitutes a review of the progress from April 27, 1959 through July 31, 1960.

Experimental results on the effect of periodic acceleration on a natural circulation, 1000 psia, two-phase flow loop are presented, and related to the topic of marine reactor design. The initial results of this work were given previously in GEAP 3397.

Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. It will be achieved by extensive development and testing carried out in conjunction with the design, construction and operation of the Big Rock Point plant of the Consumers Power Company in Michigan. This second quarterly report describes the progress achieved from July through September 1960.

The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.

From introduction: "This is the second of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."

From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."

It is proposed in this report to describe a new two-phase flow mixing length model. It consists of treating the two-phase system as a continuous medium and applying to it the methods and assumptions so widely accepted in single-phase turbulent flow. Because it reduces a two-phase problem to an equivalent one in single-phase flow, the proposed model can be readily used to predict the effects of flow rate, channel geometry, and channel direction in two-phase flow.

This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.

Information obtained in a survey of control rod applications and operating experience is reported. This survey covered the Army Nuclear Power Program, the Organic Moderated Reactor Experiment, the Yankee Atomic Power Plant, the Shippingport Pressurized Water Reactor and the Argonne Experimental Boiling Water Reactor.

From introduction: "This report provides the preliminary design for the nuclear portion of a 300 MWe Boiling Water Separate Superheater Plant to be in operation by 1967."

VARI solves on the IBM-650 a system of simultaneous, first-order, ordinary, differential equations. The program was written so that a large number of calculations could be done in a reasonable length of time. The program permits the consideration of the production of the isotope by absorption and/or decay of one or more of any of the other isotopes in the chain.

The fabricability, elevated temperature strength, steam corrosion resistance, and hydrogen pickup of various binary, ternary, and quaternary alloys were studied experimentally.