A critical analysis of the Al-Ni-U bond and the hot die size bonding technique is given as the result of a literature search. Metallurgical aspects of the bond and the technique of hot die sizing are commented upon in particular.

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Effective use of known experimental design principles in planning nuclear-radiation-effects experiments associated with engineering development programs assures that necessary, useful information will be obtained from the characteristically costly and the time consuming radiation-effects tests. This report discusses the principles of experimental design and illustrates their compatibility with nuclear-radiation-effects experimentation by presenting a model experimental design for a hypothetical nuclear-radiation-effects experiment.

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Extensive precipitation was observed in S8ER cladding following irradiation. Electron microprobe analysis was proposed as a means to identify these precipitates. Subsequently, the electron microprobe was successfully used for qualitative analysis of unirradiated and irradiated S8ER cladding. The unirradiated, thermally aged control specimen analyzed showed two major precipitates. One, a randomly distributed intergranular phase, contained Ti, Mo, Fe, Cr and Ni and a second, a randomly distributed intragranular phase, contained Si, Mo, Fe, Cr and Ni. The irradiated specimen analyzed showed the same precipitates. The phase containing Ti, Mo, Fe, Cr and Ni was also randomly distributed intergranularly. The phase containing Si, Mo, Fe, Cr and Ni was in the grain boundaries, and preferentially segregated to the outer and inner diameter.

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The effectiveness and corrosion characteristics of Turco 4512-A, an inhibited phosphoric acid, are being evaluated for N-Reactor primary system carbon steel decontamination by in-reactor decontamination tests, full scale component evaluations, and laboratory corrosion tests. To date these tests have showed that the decontamination procedure is effective for carbon steel decontamination and safe for all primary system materials that will be contacted by the solution. A few materials, namely, 17-4 pH SS, 416 SS, 420 SS, and Easy-Flo 45 braze alloy have not yet been completely tested. Results of their performance will be reported prior to full reactor decontamination.

In September of 1965, a program was launched to investigate the cause and to determine appropriate corrective or preventive action for hydriding of Zircaloy process tubes in K Reactors. One phase of the investigation was specifically directed to the measurement of galvanic corrosion currents flowing between the Zircaloy process tube and the aluminum spacers. Production Test IP-807 authorized in-reactor galvanic test measurements in order to secure data relating to the hydriding problem. It is the purpose of this report to document all the galvanic corrosion current data recorded for tests in K Reactors during the investigation of the hydride problem. The galvanic potentials recorded for test measurements in the K Reactor process tubes, identifies the approximate location and magnitude of the corrosion currents generated between aluminum spacers and Zircaloy process tube. The flow of galvanic currents and subsequent release of hydrogen gas can be related to the hydriding of the Zircaloy tubes. The data enclosed in this report indicate a substantial amount of galvanic action in the downstream dummy section of the process tube. The use of certain metal coatings on the aluminum spacers could reverse the galvanic cell polarity and cause corrosion of the process tube which would not …

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Declassified 21 Sep 1973. The following were studied: mechanical properties of WUO/sub 2/ -- ThO/sub 2/, Mo --54UO/sub 2/ --6ThO/sub 2/. W--3Re -- 54UO/sub 2/ -6ThO/sub 2/, Mo--50Re, W--30Re--3OMo, Ta and Ta --8W--2Hf; thermal expansion of W-25Re--30Mo and unclad and Ta-clad W--54UO/sub 2/--6ThO/sub 2/; and electric conductivity of Ta tubing and Ta-clad W--54UO/sub 2/-6ThO/sub 2/. (DLC)

It was noted previously that 3-(p-dimethylamino)-2-phenyloxaziridine (I) and 3-(p-dimethylamino)-2-(m-nitrophenyl)oxaziridine were photosensitive. Further study on the irradiation (in a variety of solvents under nitrogen) of (I), 2,3-diphenyloxaziridine (II), and 3-(p-nitrophenyl)-2-phenyloxaziridine (III) indicates the major photoreaction to be cleavage to the aldehyde and an intermediate which forms aniline and azobenzene. There is also formed in the photolysis varying amounts of the corresponding anilide. A table provided gives the yields in three different solvents.

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The purpose of this report is to present the results obtained from a study to determine the most economic K Reactor graphite temperature for assumed helium loss rates and the economic incentives for reducing the helium gas losses at these reactors.

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This document details activities of the Mound Laboratory Isotopic Power Fuels Program during the months of April, May, and June 1967.

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This monthly report details activities of the Battelle Pacific Northwest Laboratory in production and Hanford Plant assistance programs for the month of July 1967.

Progress is reported in these areas: CIVILIAN POWER REACTORS; APPLIED AND REACTOR PHYSICS; REACTOR FUELS AND MATERIALS; ENGINEERING DEVELOPMENT; PLUTONIUM UTILIZATION PROGRAM; NUCLEAR SAFETY.