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Report providing information about experiments performed on core samples taken from the Tatum Salt Dome in Mississippi with an appendix about similar core samples from Louisiana. "All samples were examined petrographically before being subjected to physical tests to develop information on texture, fabric, structure, and composition" (p. vii).

This report addresses comments on "Request for Proposal" and digital data system functional specifications and attachments "A".

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This report describes some present practices in regard to power calibration techniques and goes on to propose an automatic calibrator based on thermal power.

Report of the U.S. Army Engineers describing the geography of Sabine Neches Waterway texas including the likelihood of floods and benefits of flood control

A plug-in-type surface ionization source has been designed and built to be used with a mass spectrometer equipped with a vacuum lock. The sample filament mounts on a male plug which fits into a female receptacle mounted on a case plate. A firm electrical contact is realized. Sample plugs are changed without loss of vacuum and can be used with any geometrically orientated analyzer tube. (auth)

Calculations on the S-wave LAMBDA -N and LAMBDA - LAMBDA interactions, binding energies for the p-shell hypernuclei, and the mesic decay and nonmesonic de-excitation of the A-particle are discussed. The theory behind the calculations, as well as the results and their interpretation, are considered. (D.C.W.)

The premature failure of fuel Element M22, which had six compartments of 0.100-in.-thick, 96% TD UO/sub 2/ + 6 wt% ZrO/sub 2/ fuel, was attributed to the large irradiation-induced solid volume swelling of the UO/sub 2/ fuels. This volume swelling was the result of incomplete homogenization during fabrication of the mixed and sintered U/sup E/O/sub 2/ and U/sup N/O/sub 2/ fuel s in Element M22. In addition, heavy hydriding of the Ni-free Zircaloy-2 cladding occurred in the relatively hot areas adjacent to the fuel and to a lesser extent at the external cladding surfaces. By postulation, H/sub 2/ was apparently formed by the radiolytic decomposition of water entrapped between fuel and cladding after formation of the initial cladding defect, and was absorbed by the cladding so rapidly that it could not diffuse adequately down the thermal gradient to the cold side of the cladding. The corrosion behavior of the cladding was as expected and did not contribute to the hydriding. Analysis of the CR-X-3 loop operating history indicates that no abnormal conditions external to Element M22 existed in the loop other than U from inpile intentionally defected fuel elements. (auth)

A search for solutions suitable for dissolving uranium dioxide powder or lumps and yet noncorrosive enough to be used for decontaminating the carbon steel EGCR charge and service machines resulted in the development of buffered oxalate solutions of controlled temperature and pH, with hydrogen peroxide added to act as corrosion inhibitor, UO/sub 2/ oxidizer, and decontamination aid. Hydrogen peroxide acts either as a corrosion promoter or inhibitor, depending on factors such as its concentration, the ratio to other ingredients, acidity, temperature, the presence of complexing agents, and the ferric ion content of the solution. In general, oxalate-peroxide solutions for fission product decontamination from metal surfaces were superior to more conventional decontaminating solutions and had attractively low corrosion rates on carbon steel (less than 0.01 mil/hr), Solution instability, initially a serious drawback, was largely overcome. Of nearly a hundred formulations studied, the one having the best combination of long life, low corrosivity, high solvency for UO/sub 2/, decontamination power, safety, and ease of waste disposal was an aqueous solution of 0.4M oxalic acid, 0.18M ammonium citrate, and 0.34M H/sub 2/O/sub 2/, adjusted to pH 4.00 with ammonium hydroxide and used at 85 to 95 deg C. Similar solutions at lower pH, …

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The experimental measurements of electron ejection in Po/sup 210/ decay are discussed, and the theory of the process is outlined. The order-of-magnitude discrepancy between theory and experiment that was evident a decade ago has not yet been definitively resolved. The discrepancy is ascribed to an inadequacy of the theory, in particular to the use of an asymptotic expansion in that theory. Brief mention is made of some very recent unpublished calculations by G. W. Schaefer in which a reasonable estimate of the K-ejection probability is obtained by a procedure that avoids the asymptotic expansion. (auth)

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Information on the properties of the nuclear interactions of hyperons, weak interactions of the hyperon ( LAMBDA ), and properties of nuclei that could be obtained by studying hypernuclei is discussed. Experiments that should be able to give relevant information in the near future are considered. (D.C.W.)

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ABS>A system was created for processing large volumes of data from Project ROVER tests at the Nevada Test Site. The data are compiled as analog, frequency modulated tape, which is translated in a Packard-Bell Tape-to-Tape converter into a binary coded decimal (BCD) IBM 7090 computer input tape. This input tape, tape A5, is processed on the 7090 by the RDH-D FORTRAN-II code and its 20 FAP and FORTRAN subroutines. Outputs from the 7090 run are tapes A3, which is a BCD tape used for listing on the IBM 1401 input-output computer, tape B5 which is a binary tape used as input to a Stromberg-Carlson 40/20 cathode ray tube (CRT) plotter, and tape B6 which is a binary tape used for permanent data storage and input to specialized subcodes. The information on tape B5 commands the 40/20 to write grids, data points, and other information on the face of a CRT; the information on the CRT is photographed on 35 mm film which is subsequently developed; full-size (10" x 10") plots are made from the 35 mm film on a Xerox 1824 printer. The 7090 processes a data channel in approximately 4 seconds plus 4 seconds per plot to be made …

The use of nuclear energy in the space programs is discussed. Nuclear rocket development is reviewed, and the Nevada rocket development station, nuclear electric propulsion and power generation, and advanced research projects are discussed. (J.R.D.)

A total of 553 references are listed on the SNAP program and related topics. The references were taken from Nuclear Science Abstracts to Dec. 31, 1962. The contents are arranged in sections on radioisotope-fueled units, reactorfueled units, direct energy conversion, and general topics on nuclear auxiliary power. (J.R.D.)

The development of foam separation as a unit operation was considered from the distributor design and gas rate standpoints. The development of a shear and leach process for power reactor fuel processing is reported in which carburized Yankee prototype fuel assemblies were sheared to determine the effect of fuel element condition on the nature of the chopped pieces. A Squarkeen No. 3 moving blade lasted for 5894 cuts while a Kleencut blade failed at 320 cuts under normal program use. A plastics and coating material testign program for the Transuranium facility is under way. The Vo1atility development program is stadying the recycle of the salt charge for Zr fuel element dissolution and has completed the fourth recycle test. The radioactive waste processing program has completed the test R-65 which studied the movement of mercury out of the calciner during the processing of TBP-25 waste. (auth)

Through addition of approximaely 0.4 wt % carbon (as zirconium carbide) to a 90 wt % Zr - 10 wt % U alloy, a 100% yield of uncracked massively hydrided fuel elements of high hydrogen density (N/sub/H ≈ 5.7 to 6.6) was obtained. The marked increase in yield was attirbuted t the presence of a carbide phase, serving as a nucleant and grain-growth inhibitor during solidification and subsequent solid-state transformations that occur during the hydriding process. The resulting hydride structure was fine grained and equiaxed.