This memorandum reports the performance of TORY II-C at off-design altitudes and Mach numbers. Inlet pressure recovery has been varied with Mach number, reasonable values for a real inlet having been chosen. Nozzle throat area and exit area have been fixed at the design values. Hence this study can be used, in conjunction with missile drag data, to construct a flight envelope.

A complete spectral representation is given for a class of singular integral operators. The influence of spectral multiplicity is partially taken into account. (T.F.H.)

The density and purity of fused UO/sub 2/ from several suppliers was evaluated. Densities of large pieces varied widely, but variations in pycnometer and bulk densities of crushed UO/sub 2/ powder were small. Average oxygen- touranium ratios ranged from 1.94 to 2.14. Impurities visible as microscopic inclusions were U/sub 4/O/sub 9/, metallic uranium, UC, and UN/sub 2/. The chief trace metallic contaminants were aluminum, iron, and silicon. Hydrogen, nitrogen, carbon monoxide, and carbon dioxide were evolved during vacuum extraction. (auth)

Progress is reported on developments in the treatment of Purex waste solutions, the extraction of ruthenium from nitric acid solutions using TPP, the calibration and performance analysis of gamma-source calorimeters, and the adsorption of iodine-131 from aqueous solutions. (B.O.G.)

The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)

The properties of radioisotope fuel compounds and fuel capsule materials which are pertinent to the design and operation of radioisotope heat sources are outlined. These properties are grouped into the following categories: intrinsic, extrinsic, and compatibility. The properties of strontium titanate as the fuel and Hastelloy C as the capsule material are evaluated. (D.L.C.)

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These data are provided: Masses and .Mean Lives of Elementary Particles; Atomic and Nuclear Properties of Materials; Particle Scattering; Atomic and Nuclear Constants; Particle Decay and Reaction Dynamics; Tentative Data on Strongly lnteracting Particles and Resonances; and Clebsch-Gordan Coefficients and Spherical Harmonics.

Eleven papers are presented on the chemistry of protactinium. Most of the emphasis is on solvent extraction and solution chemistry. Separate abstracts were prepared for ten of the papers; the remaining paper was previously abstracted in NSA. (D.L.C.)

A series of in-pile experiments was designed for evaluation of a prototype fuel element to operate under approximate ASCR conditions. The fuel surface temperature will be automatically controlled by means of a BF/sub 3/ thermal neutron flux control system. Complete design calculations and results are presented, which should be adequate for presentation of the experiment to the ETR safety committee. (auth)

A total of 68 Swiss albino mice of either sex were thy; mectoraized at the following time intervals after birth: 22 during day one, 21 during day two, 17 on day four and 8 on day eight. Sixty-one nonoperated litter-rnates served as controls. All mice were given primary andtigenic stimulation with adsorbed tetanus toxoids when four weeks of age. Three weeks later a booster injection of fluid tetanus tokoid was given. With these time intervals thymectomized mice showed only slightly impaired primary responses but severely repressed secondary responses as compared to nonoperated litter-mates. This uncommon finding is difficult to explain at present and results are discussed with regard to other reports on the effect of postnatal thymectoniy on immune responses. Special emphasis is placed on the unknown effect of postthymectomy wasting syndrome. (auth)

MOUND LABORATORY PROGRESS REPORT FOR APRIL 1963. (Abstract too long to run in Kurzweil program)

This report addresses the decay heat cooling analysis of a nuclear rocket engine.

A process was developed for the destruction of HNO/sub 3/ in Purex-type waste solutions using sugar. Polyhydroxy compounds such as sucrose, fructose, glucose, and crude syrups such as black strap molasses rapidly and controllably decompose HNO/sub 3/ in aqueous solutions at temperatures above approximately 85 deg C. The number of moles of HNO/sub 3/ destroyed per mole of sugar fed is a function of the temperature of reaction and the moles of dissolved multivalent metal cations (such as iron and chromium). The efficiency of HNO/sub 3/ destruction does not vary with acid concentration over the range of 0.5 to 8 M. However, destruction of acid does vary with iron concentration. Approximately 12 to 20 moles of HNO/sub 3/ are destroyed per mole of sucrose fed as the iron concentration increases from 0 to 1 M. Products of the denitration reaction are all gaseous, consisting of oxides of carbon and nitrogen. The process was successfully tested in the high level hot cells, the cold pilot plant denitration unit, and in the Purex plant. (P.C.H.)

A process was developed on a laboratory scale for recovering, in 90 to 95% yield, I/sup 129/ from Berl saddles impregnated with AgNO/sub 3/. The iodide ion is displaced from silver iodide by sulfide ion in alkaline solution, and I/ sup 129/ is distilled from the 1M NaOH-0.01M Na/sub 2/S solution after oxidation with hydrogen peroxide. (auth)

The chemical potential of the brine from I.I.D. Well No. 1 was evaluated and reported in Rogers Engineering Coo, Inc. March 1962 Flow Test Report. This evaluation considered only the recovery of sodium chloride, as the prime salable product and alternately as the raw material for conversion to salable chlorine and caustic. Both cases showed low net revenue relative to the estimated capital investment required. The subsequent three month well flow test indicates continued production of a consistent type brine can be expected from this well. Based on the flow and composition data established during this test period, chemical production potential has been examined. The separation and sale of high quality potassium chloride appears attractive. Attached are sketches of each of the two production schemes considered with estimates of capital and operating costs and revenue.

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The purpose of this test was to determine the amount of deflection which could occur into the graphite cavity with a .032" thick sheet of 2219-T31 aluminum alloy.

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This report explains details of the Advanced Materials Program. The purpose of this program is to develop improved alloys for nuclear powerplant structural applications in the 16000F to 2000F range and for advanced applications at temperatures to 2400F or above.

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Hydraulic and deflection analyses of the unequal flow passages in the HFIR control region revealed excessive pressure differentials. A proposal to drill connecting holes between the flow passages initiated an experimental program for investigating the effectiveness crossflow on pressure equalization. Empirical constants for an analytical model and experimental design data on reduction of pressure differentials between channels were obtained. It was determined that crossflow between channels would satisfactorily reduce the pressure differentials. (auth)