An eddy current test system is described in which the test information is detected as a series of fields reflected from the metal surface and interior. Pulsed electromagnetic fields are caused to impinge upon the test specimen. These fields are restricted to a small cross sectional area over a path in space long enough to be useful for test purposes by devices called mask-apenture assemblies. This approach provides a number of advantages over conventional eddy current methods of comparable capabilities, including superior surface resolution, a reduction in circuit complexity, and an improvement in stability and reliability. Various applications and test results are discussed. (auth)

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A half-plant low alum treatment test began at F Reactor on January 16, 1963. The test, which had been prompted by results obtained from a statistical analysis of fuel element ledge corrosion attack, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from normal production fuel irradiated in process water treated with two different alum feed rates. This report presents the results from 20 fuel charges, ten from each side of F Reactor, which were discharged such that the near side fuel pieces had been exposed for 75 days to water treated with 18 ppm alum and the far side pieces had been exposed 75 days to water treated with 8 ppm alum.

This report discusses nuclear processes involved in heavy isotope production in the N-Reactor. Production methods, production rates, and the nuclear advantages of the N-Reactor are presented.

This report describes the analysis performed in determining the lowest pemissable insulation resistance for the exposed junction copper/constantan thermocouples to measure outer reflector drum annulius, drum vane and beryllium exit gas temperature.

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A simple method is developed for calculating or predicting temperature distributions in spent reactor fuels in shipping casks. The method accounts for radiant heat transfer between all the individual pins in a square array. With the dimensions of the fuel bundle, the configuration factors for radiation between various tubes in the bundle can be obtained from the tabulated numerical calculations presented. The configuration factors, along with the heat generation rates, surface emissivity, and the temperature of the wall of the cask can be used to estimate the temperature distribution automatically with the computer code presented or possibly by hand calculations by the method outlined. Experimental measurements of temperature distribution in electrically heated tube arrays in steel shells that simulated shipping casks were made to test the proposed calculational procedure. Several heat generation rates and bundles containing up to 64 tubes were tested in 12-in.- and 6-in,-inner diameter shells. Tests were made with the casks in horizontal and vertical positions. The predicted temperatures were very near those observed experimentally under the conditions in which heat transfer is likely to be a problem in fuel shipment, that is, when the temperatures are near or above 200 c- C and the casks do …

The report addresses the analysis of check value including failure and recommendations.

This report summarizes the results of apparent strain tests conducted on both temperature-compensated and uncompensated Microdot weldable strain gages as requested by the Sensor Application Engineering group.

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The visual material presented on the SNAP-50 reactor components cover the reactor and shield, Rankine cycle boiler, materials, high-temperature instrumentation, and pump. (DLC)