This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.

This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.

Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.

This report summarizes progress on investigation into improving the technological limits of boiling water reactors, Vallecitos Boiling Water Reactor and other facilities.

The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding if the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely fission gas release and central melting in fuel rods.

The General Electric Company is proceeding with an irradiation program to proof test a representative array of Savannah I fuel rods. Irradiation of a test assembly containing Savannah I fuel rods has begun and it is proposed that the results of this irradiation will permit an advance evaluation of the fuel performance and fuel burnup in the Savannah I reactor. This report covers the first two quarters of the reporting period. All aspects of the subject program have been consolidated and applicable portions are discussed in some detail.

Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.

A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.

The objective is to establish, from test results, the relationship between pressure loss and orifice configuration, mass rate, and steam quality, for a Fuel Cycle fuel assembly.

Writing the VARI-II Program was motivated by the need for a method of analyzing the results for the Absorber Burn-Up Experiment in progress at the Vallecitos Atomic Laboratory.

The basic work for development of a scheduling computer for the Consumers' Big Rock Plant is outlined in this report. The computer's purpose is to make feasible higher power densities by operation closer to fuel element burnout limits, and to maximize fuel burnup.

The pressure drop of a new fuel element design concept of spacing rods by means of helical wire springs was investigated experimentally and analytically.

The fourth quarter of effort applied to the Consumers R & D Program is summarized in the following: high power density fuel development, fuel fabrication development, stability, heat transfer and fluid flow, physics development, operation planning and test coordination.

Experiments were carried out to determine the erosion, oxidation and dimensional characteristics of purposely defected fuel elements containing unsintered UO2 powder prepared by the swaging technique. The experiments were conducted in an out-of-reactor loop under superheat conditions of pressure, temperature, flow velocity and steam chemical composition.

A better understanding of the maximum operating characteristics that can be achieved with the use of UO2 as a reactor fuel is the primary purpose of this program for Euratom and the Atomic Energy Commission. During this program work will be undertaken in two areas that have been of concern to the reactor core designer for a long time, viz. fission gas release and central melting in fuel rods.

Stability tests are to be made in the VBWR (boiling water reactor). The tests are of three types: steady state measurements, rod oscillator tests, and transient tests.

From introduction: "this is the fifth 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 sixth 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 seventh 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: "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."

This Preliminary Hazards Summary Report has been prepared for submission to the United States Atomic Energy Commission in compliance with Part 50 of the regulations governing the licensing of production or utilization facilities, pursuant to the Atomic Energy Act of 1954, as amended, and contains the general information required by 10 CFR 50.34.

This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.

This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the first quarter of fiscal year 1962. The data are summarized in Section II.

During the quarter the development program was continued as scheduled. Milestones that were reached included the successful irradiation of prototype Big Rock fuel bundles in VBWR to a level above 2500 MWD/T with power densities as high as 88 kw/1. Also completed was the scheduling computer specification followed by a formal solicitation of bids through the AEC. A summary of progress by task is presented here.