The complete electrostatic and spin-orbit matrices of the f/sup 5/ electron configuration were calculated and are presented tabularly. (auth)

A description of the EBR-II shield and the methods employed in arriving at the final design are presented. The major shield design problems for that reactor are enumerated and discussed. (auth)

Operation of the Lampre I during the report period is described and data on the operating history of this reactor are summarized. Other work is reported on core calculations, fuel and container development, and compatibility of Pu-Co- Ce alloys with Ta. Studies of the physical properties of Pu alloys with C, ln, Si, and rare earths are described. Data on the room temperature densities in the Pu-Ce-Co alloy system are presented. Solvent extraction studies concerning separation of Pu are included along with results of electrorefining of irradiated Pu fuels. The developmental status of the core test facility is reported. (J.R.D.)

Chemically purifled Zr/sup 95/ was used in determining selfdiffusion coefficients in the body-centered cubic phase of iodide zirconium over the temperature range of 900 to 1750 deg C. In order to minimize effects of build-in of the daughter isotope Nb/sup 95/, all heat treatments were completed within 48 hr after the purification. The temperature dependence of the diffusion coefflcients could not be described by the usual Arrhenius-type equation. Instead, apparent values of the frequency factor D/sub o/ and the activation energy Q varied from 4.8 x 10/sup -6/ to 2.5 x 10/sup -2/ cm/sup 2//sec and 20700 to 46900 cal/mole, respectively, between the lower and upper extremities of the temperature range. Empirical treatment of the data indicated that Q is a linear function of temperature and that D/sub o/ varies with a power of the temperature. The data may be described in terms of the alpha to BETA transition temperature of 1136 deg K and the absolute temperature of the heat treatments by the following equation: D = 3 x 10/sup -6/ (T/1136)/sup 15.6/ exp (--19600 + 31(T -1136)/RT) cm/sup 2//sec. (auth)

The climb rate of prismatic dislocations in quenched Al-5% Mg Alloy was studied by bulk annealing and also by high-temperature electron microscopy of thin foils, In bulk and thin-foil specimens, loops and helices were always observed to grow. The activation energy was determined to be 0,95 plus or minus 0.05 ev. The results can be interpreted on the basis of a binding energy between vacancies and magnesium atoms which can be x0.1 to 0.4 ev, depending on their geometrical configuration. (auth)

The effects of uncertainties of nuclear data on the calculation of integral quantities for some fast breeder systems were evaluated. The integral quantities chosen were reactivity, initial breeding ratio, and initial internal breeding ratio. The fuels chosen were Pu/sup 239/-U/sup 238/, both as metal and oxide, and U/sup 233/-Th as oxide. The importance of propagation of errors on the uncertainty in reactivity was determined. Results indicated that because of inaccuracies in the values of nuclear parameters as known within the present state of the art'' the deviations of the calculated reactivities should be about, and possib1y larger than, 2% DELTA k/k for all the medium and large systems considered. The deviation of the initial breading ratio is 3.5%, and for the initial internal breeding ratio it is about 5%. The consequent uncertainty in the calculated critical mass is of the order of 4%. (M.C.G.)

A study was made of the preparation of alpha, gamma, and neutron sources using the long-lived radioisotope of americium, Am/sup 241/. Americium-241 is an artificiallyproduced radioelement which has a half-life of 462 plus or minus 10 years and decays to Np/sup 237/ by alpha emission followed by low-energy gamma emission. The high specific activity of americium-241 (7.0 x 10/sup 9/ d/m/mg) combined with its reasonably long half-life makes it ideally sulted for the preparation of radioactive sources. The chemical and physical properties of Am/ sup 241/ and the physical manipulations involved in fabricating alpha, gamma, and neutron sources are generally described in this report. Uses for each type of source are discussed and data are presented to indicate the respective properties and usefulness of each source type. (auth)

Discrete quadrature weights and angles for use in discrete ordinate methods of solutions for thin cells were tabulated for a series of regional cell thicknesses of applicability. Parameters are given for 4, 8, 8, 10, and 12 angle approximations. The quadrature assignment was based upon a simplified integral transport solution to the spatial average of the angular distribution of uncollided flux, assuming flat sources. The quadrature assignments are designated TRIM, for thin-region integral method, and are most useful with thin cells having either or both regions very thin in mean-free-path units. The IBM- 704 Fortran program used to compute the parameters is described. (auth)

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