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Title: REACTOR TECHNOLOGY REPORT NO. 20-METALLURGY

Technical Report ·
OSTI ID:4783451

The nickel-chromium-iron alloy, usually designated by its trade name Inconel, has found increasing application for use in power generating equipment operating at temperatures up to 600 deg F. A summary is made of the mechanical properties, corrosion behavor, and manufacturing characteristics of this alloy. The data presented were compiled from a number of references and are the results of investigations conducted since 1958. A procedure is described by which reactor grade Zircaloy-2 ingots can be produced at a cost saving by utilizing light and medium gage wrought Zircaloy-2 scrap. Existing facilities are capable of performing the scrap recovery process without further development. Since certain fabrication procedures result in only two or three grains across the thickness of Zircaloy-2 strip material, an investigation was conducted to determine if a small number of grains across the section thickness is detrimental to the strength. Room temperature and tensile properties were determined on rolled Zircaloy-2 sheet of three thicknesses, two grain sizes and two heat- treatments. Results indicated that for a given grain size there is a decrease in strength and ductility with decreasing thickness. Alloys of Zircaloy-2-niobium- oxygen occur in certain reactor cores. Alloys of Zircaloy-2 with 0 to 7.5 wt% niobium were prepared, and oxygen was added in amounts from 700 to 3500 ppm. Notched and unnotched tensile properties of these alloys were determined at temperatures between room temperature and 850 deg C. From the results obtained it is possible to predict the notched and unnotched tensile behavor of Zircaloy-2 alloys within the limits of 7.5 wt% niobium at 3500-ppm oxygen. A comparison of standard wire sieves, precision-etched square-hole sieves, and precision-etched sound-hole sieves in separating ceramic and metal particles was made by using average particle size and distribution, surface area and shape-factor measurements as the major physical properties for correlation. A Coulter liquid resistor particle size analyzer was used as a standard for the accurate determination of particle size and distribution. The Carman-Xozeny permeability principle was applied in the measurement of surface areas. A method of calculating x-ray density reported in the litere was applied to enriched UO/sub 2/ . It is shown that the :ect x-ray density of enriched UO/sub 2/ can be calculated never the isotopic analysis of the UO/ is known. The res of an investigation to determine the effects of lithium in the boron-carbon system are summarized to provde a basis for evaluation of irradiated boron carbide. An investigation of the alloy system was made by using x-ray, petrographic, and chemical methods. The presence of a n-lithium compound was detected. For accurate neuflux distribution measurements in nuclear reactors by er and titanium flux wires, the wire diameter must be to close tolerances and inspected to within plus or minus 0.0001 in. The development of an eddy-current gage for diameter measurement of copper wires is summarized. An instru ment was developed to continuously measure and record the diameter of 0.020-in.-nominal copper wire with a threesigma (35) precision of 0.000081 in. (auth)

Research Organization:
Knolls Atomic Power Lab., Schenectady, N.Y.
DOE Contract Number:
W-31-109-ENG-52
NSA Number:
NSA-16-015184
OSTI ID:
4783451
Report Number(s):
KAPL-2000-17
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English