This statistical analysis examines volume increase data from PTA-040. The purpose of this analysis is to compare four 1.25 enriched uranium core alloys (Standard, British, High Silicon, and Modified British), two heat treatments (Induction and Salt Bath), and the alloy-treatment interaction. The four core alloys were each processed using the two treatments and then canned as 5.540-in. AlSi fuel elements. Test pieces were charged in 16 tubes with 40 pieces per tube. The eight fuel types (4 alloys {times} 2 treatments) were arranged in a series of Latin squares in the test tubes to eliminate the effect of position and tube. A comparison of volume increase was deemed worthwhile after analyzing PTA-040 with regard to fuel element distortion. Volume increases in the present analysis were calculated by H.D. Huber using OD and ID measurements taken at C-Basin with consideration for can wall corrosion and geometric distortion. these volume increase calculations were not completely substantiated, since a thorough check with water displacement measurements at the Radiometallurgical Laboratory was not possible. Despite this fact, the present analysis was continued since a good correlation between the volume increase calculations and element exposure was observed.

A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this possible approach appeared warranted. This report summarizes the results of this test. Samples taken from each effluent riser during reactor operation indicated no improvement in either As{sup 76} or P{sup 32} performance. This comparison is shown below with a complete tabulation of daily values included as Attachment 1.

This document presents details about the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of November 30, 1969.

From time to time, in discussion of possible naval-based nuclear ramjet missile systems, a question arises concerning whether or not a particular reactor would or would fall within the `Tory II-C Technology`. Such a question is meaningless unless a definition is furnished. This report provides such a definition.

A study of relative plutonium and orallay values is being made by representatives of the production sites under direction of AEC Headquarters. Division of Production. (Oralloy is uranium enriched to 93-15 percent U-235.) Under study assumptions that will be detailed later, oralloy would cost less than formerly, and may be cheap enough to enrich production reactor discharged uranium to reactor input assays. To date uranium recycle enriching assays have been held below two percent U-235 -- usually 1.2 to 1.5. Use of orallay for enriching reactor tails would conserve U-236. which would increase neptunium and Pa-238 production. There may be other profitable reactor uses for the cheaper oralloy.The intent of this document is to give the oralloy cost data to those who may study or evaluate oralloy use, and to explain the basis for oralloy cost so that the validity of any use may be assessed.

An evaluation of several alternate ways to redesign the Prototype Steam Generator to eliminate stainless steel pressure parts is being made. Recommendations will be made to the Commission. Fabrication of the Prototype is held up. A draft of the Interim Report containing design criteria, steam generator preliminary cost trend curves and preliminary specifications has been submitted to the Commission for approval.

The specific impulse achieved in a pulsed rocket engine augmented with a fissioning nuclear bomb could be greater than that of any continuous flow engine. To a certain extent, this increase in specific impulse would be obtained at the expense of motor weight and average thrust. This paper considers the first of these limitations, motor weight, and estimates the highest effective specific impulse to be expected from a nuclear-pulsed rocket motor with respect to the weight of the motor.

The Heating and Ventilation System provides the atmospheric conditions in FFTF as required to assure that plant objectives can be met in a safe and practical manner. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

Abstracts are provided for presentations in these areas: studies in immunology; studies in molecular biology; experimental and clinical studies of cell differentiation; studies on the blood; general metabolic studies; problems in scanning; clinical and experimental studies on the effects of radiation; and studies with high energy radiations.

The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

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This report addresses the control design review of P&W quarterly for July to September 1960.

A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

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A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

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A commercial graphite useful in nuclear reactor construction is described. A survey of all currently available sources on chemical and physical properties was made and the information listed. Some data on cost and available sizes are also included. (auth)

The preliminary design is described of equipment to carry out experiments on boiling burnout in which the average coolant density as a function of coolant channel length as well as local coolant densities may be measured. It appears that by use of the equipment, average densities can be accomplished in a few seconds, while determination of a complete density map (with 5% error) across a plane of the assembly requires approximately one hour. (J.R.D.)

In connection with the ORR Hastelloy-N irradiation experiments, a limited number of tensile tests and uniaxial and biaxial stress-rupture tests on S8DR Hastelloy-N heats were conducted at AI to determine the effect of some of the ORNL test conditions. The tests performed at AI were in parallel to the ORNL control tests. The results showed that the effect of the test condition variations between the two tests were generally insignificant. The effect of the test conditions is discussed.

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