The choice of materials and other vessel design decisions necessary to provide the desired life expectancy for the FTR vessel are partially dependent upon estimates of the number and type of reactor shutdowns and startups which may be anticipated. Current estimates of these so-called "cycles" are given, including scram frequency, experimental outage frequency, standard shutdowns and startups, and rapid controlled shutdowns. Also discussed are abnormal heatup or cooldown, and tentative goals for temperature controls. MTR, ETR, and typical PRTR operating histories are tabulated.

Primary, secondary, and thermal stresses were calculated and evaluated for the SNAP-8 developmental reactor fuel element cladding. The effects of fabrication and assembly stresses, as well as test and operational stresses were included in the analysis. With the assumption that fuel-swelling-induced stresses are nil, the analytical results indicate that the cladding assembly is structurally adequate for the proposed operation.

This addendum provides primarily the information relative to waste management as called out in the unclassified report. This information is provided in the following tables. In addition to the gaseous radionuclides (Ar-41, I-131, H-3) noted in the unclassified report, krypton and xenon are also released during dissolution of fuel. The chemically inert character of these elements prevents their removal by the usual off-gas treatment, but at the same time also prevents their uptake by biological species. Thus, these radionuclide contribution to personnel dose is only through direct exposure to stack effluent. Dilution by the atmosphere effectively reduces the concentrations of all these gases so that they are undetectable beyond the reservation boundaries. Radioactive krypton and xenon contribute essentially nothing to radiation dose off-site and very little on-site.

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A study was made to determine the flow rates and pressure drops for all primary system flow paths through the FTR. The main data and results are in tables, diagrams and curves. The results are intended to provide a common basis for evaluation of parametric changes in the system.

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The FTR vessel wall will be cooled with inlet primary coolant which bypasses the core and flows through an annulus formed by the vessel wall and the thermal barrier. heat transfer to the by-pass coolant stream is by raial conduction from the surrounding sodium pool through the thermal barrier wall. In the analysis, the temperature rise of the by-pass coolant stream was derived as a function of the wall thickness of the thermal barrier and the flow rate of the by-pass stream.

The major technical bases for the FFTF first core fuel assembly conceptual design are presented in four general categories: (1) thermal, (2) hydraulic, (3) structural and (4) performance-manufacturing design characteristics. Recommended design values and conceptual engineering drawings of the fuel pin and subassembly are included .

This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

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An electronic computing gage with IBM card punch was found to be a practical system for monitoring the critical steps in the crimping process of the assembly of some parts. In the crimping process a plastic part is compressed into a metal cup to obtain an assembled component without gaps. Dimensional data of the plastic part and metal cup are recorded on a printed tape and on IBM cards, which are used to program a computer to calculate the standard deviation of the lot. Lot acceptance is statistical and is based on the standard deviation of the lot. The electronic computing gage compares the height of the assembled components before and after crimping and indicates whether or not an acceptable assembly (without gaps) has been made. This system eliminates the need for the manual calculation of height and recording of data at the production site, thereby increasing the reliability of the assembly process at a decrease in cost.

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