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The processing of nuclear rocket (Rover) fuels requires high concentrations of hydrofluoric acid and nitric acid in the dissolver solution to dissolve the uranium and niobium. The resulting dissolver solutlon is highly corrosive and requires the addition of aluminum nitrate to complex the free fluoride'' and reduce corrosion on stainless steel processing equipment located downstream from the dissolver. The dissolver solution is very sensitive to aluminum nitrate addition; excessive aluminum nitrate results in precipitation of Nb/sub 2/O/sub 5/. Insufficient aluminum nitrate results in precipitation of AlF/ sub 3/, and the solution remains corrosive. The stability range of the complexed dissolver solution is narrow and time dependent. The stability range was determined expenimentally to vary from 24--30% for a 2-hr period and from 0-10% for a 24-hr period. The stability range is increased to 40% over a 5-day peniod when the solution is diluted and adjusted for solvent exrraction feed. (auth)

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This report lists 42-group, coupled, neutron -gamma cross sections for H, D, T, /sup 3/He, /sup 4/He, /sup 6/Li, /sup 7/Li, Be, /sup 10/B, /sup 11/B, C, N, O, Na, Mg, Ai, Si, Cl, A, K, Ca, Fe, Cu, W, Pb, /sup 235/U, /sup 238/U, / sup 239/Pu, and /sup 240/Pu. Most of these materials are used in nuclear- weaponseffects calculations, where the elements for air, ground, and sea water are needed. Further, lists are given of cross sections for materials used in nuclear weapons vulnerability calculations, such as the elements of high explosives as well as materials that will undergo fusion and fission. Most of the common reactor materials are also listed. The 42 coupled neutron-gamma groups are split into 30 neutron groups (17 MeV through 1.39 x 10/sup -4/ eV) and 12 gamma groups (10 MeV through 0.01 MeV). Data sources and averaging schemes used for the development of these multigroup parameters are given. (119 tables) (auth)

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The successful application of a mass spectrometric method to determine the source of oxygen diffusion into the container material of a radioisotopic fuel capsule is described. The source was chiefly the oxide fuel (/sup 238/PuO/ sub 2/) and not the atmosphere. This could be accomplished by determining the / sup 18/O//sup 16/O ratio in the tantalum alloy material, because the /sup 18/O content of the fuel had been reduced to minimize alpha -n reactions. The /sup 18/O//sup 16/O ratio was ~5.5 x 10/sup -4/ for fuel as compared with 2 x 10/sup - 3/ for air. The radiochemical method, based on an alpha -n reaction, could not be applied because of the very low alpha -particle flux in the liner material. (auth)

Two aspects of a coal-tar pitch were studied: (1) reproducibility of the properties of as-received pitch as a function of the sampling period, and (2) changes in the properties that occur on heating the pitch for extended periods at elevated temperature. Reproducibility studies were conducted on twelve samples which had sampling histories that divided them into two groups of six samples each. Data indicated little variability of properties within a sample group, but significant variability between the two groups. A single lot of coal-tar pitch was analyzed as a function of residence time in an impregnator at 235 deg C. Properties reflecting increases in molecular size underwent gradual changes with increasing heating time, but the overall changes after 88 days did not appreciably alter the properties or utility of the pitch. (auth)

Prior to the issuance of construction permits or operating licenses for nuclear power reactors, the U. S. Atomic Enengy Commission is required by the National Environmental Policy Act of 1969 to prepare Detalled Environmental Impact Statements. These statements contain analyses of the balance between benefits and costs of the proposed action, including the radiological impact of operation of the facillty. Methods for computing environmental radiation doses are described. A simplified model for calculation of radiation doses from radioactive effluents was developed and programmed into a conversational language, providing the fast turnaround time required. The new model is divided into four independent parts, each written as a separate program: ARRRG: calculates individual and population doses from liquid effluents; CRITR: calculates internal radiation doses to four common classes of aquatic organisms and to onganisms which consume them; FOOD: calculates doses from consumption of food crops and animal products produced on irrigated farms; and GRONK: calculates doses from gaseous effluents, to individuals and to the total population within 50 miles. The model can be used to calculate radiation doses to the total body and selected organs of individuals and population groups, and to organisms other than man. It includes all air and liquid …

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Glass-forming and thermal treatment processes for the glass liners of bore holes produced by Subterrene rock-melting penetrators are considered. Analytical and numerical calculations of the radial temperature distributions and glass cooling rates are reported for the glass-like liners created by laboratory penetrators operating in local Los Alamos tuff and basalot. The temperature calculations are compared with experimenotal data. The cooling rate at the inside surface of othe glass liner is strongly influenced by the penetrator afterbody and stem design. To minimize residual stresses in the cooled glass, a qualitative correlaotion is found between this cooling rate and othe thermal properties of the parent rock. The magnitude of residual strains and stresses in glass produced by laboratory penetrators is estimated. (auth)

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The elementary reactions occurring in an H/sub 2/-F/sub 2/ explosion are given with each vibrational level of H/sub 2/ and HF considered as a separate reacting species. Rate coefficients for all the elementary reactions are either estimated or calculated, and the major assumptions entering into the determination of each rate coefficient are given. The effect of non-Maxwell distributions in the translational energies of some of the species is estimated. For strong pulses of F atoms, the explosion is complete before any appreciable contribution to the rate is made by thermal dissociation of F/sub 2/ or H/sub 2/. (auth)

Several alloys were evaluated as possible construction material in chemical processing equipment for plutonium at Rocky Flats. Corrosion studies were made of these alloys in solutions obtained from a production storage tank. The principal components of these solutions were RNO/sub 3/, HF, and Pu. Results showed relative concentrations of these components can significantly affect corrosion rates. Of the alloys tested, lnconel 690 exhibited the lowest corrosion rates in the process solutions. E-Brite 26-1 also showed corrosion resistance greater than 304L stainless steel. (auth)

This report describes and presents the results of an analysis of the performance of the infrared acquisition system for a Self-Initiated Antiaircraft Missile (SIAM). A description of the optical system is included, and models of target radiant intensity, atmospheric transmission, and background radiance are given. Acquisition probabilities are expressed in terms of the system signal-to-noise ratio. System performance against aircraft and helicopter targets is analyzed, and background discrimination techniques are discussed. 17 refs., 22 figs., 6 tabs.

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In experimental Task 9, the fission rate in low-enriched UO/sub 2/ fuel pins and the neutron absorption rate in the boron of a simulated lumped burnable poison (LBP) material in a critical assembly are being measured. These rates are being compared for a few select core positions and for two types of LBP pins. (auth)

The following research is reported: thermal conductivity of electron- irradiated and additively colored MgO; thermal conductivity of Pb films in the intermediate state; thermal conductivity of neutron-irradiated pyrolytic graphite; specific heat of (CH/sub 3/)/sub 4/NMnCl/sub 3/; and thermal conductivity of normal and superconducting Pb-- Tl alloys (1 and 20% Tl). (22 references, 10 figures) (DLC)

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The results of an experimental study of axial and crossflow velocity in a 7-pin wire wrapped bundle similar for FFTF fuel bundles are reported. The results are compared with the forced crossflow model of the COBRA-III C computer program. (JWR)

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A conceptual design study of 200-GeV proton intersecting storage accclerators with room temperature magnets is presented. The key to this study was thc desire to keep the electric power consumptiom to an acceptable level (40 MW). The design has been optimized by choosing small-gap (4 cm) aluminum coil dipoles operating at about 15 kG. The luminosity of this machine is limited to about 10/sup 32/ cm-/sup -2/ sec/sup -1/ by transverse space-charg e effects. An order of magnitude higher luminositics can be obtained by adding a booster of modest cost. A novel vacuum system using distributed Ti-sublimation pumps results in considerable savings. A cost comparison with a high-luminosity superconducting machine is given. (auth)

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