A total of four sections containing technical data is included in the report. Separate abstracte were prepared for each section. (J.R.D.)

Research progress at Argonne Cancer Research Hospital is reported in 23 papers. Separate abstracts were prepared for 12 papers. Eleven papers were previously abstracted for NSA. (M.C.G.)

A semiautomatic film badge system was developed to process dosimeter film faster and more reliably than the previously used manual method. The films are automatically loaded and unloaded from the badges and marked with identifying numbers, manually developed, and automatically read. The resultant information is punched into IBM cards. (auth)

Potential nuclear fuels in the system ZrO/sub 2/-CaO-UO/sub 2/ were investigated. Cubic fluorite-type solid solutions, as indicated by x-ray diffraction patterns, were formed by sintering CaO-stabilized ZrO/sub 2/ and U/ sub 3/O/sub 8/ compacts in either air or H/sub 2/. A continuous solid solution was found between urania and stabilized zirconia with H/sub 2/ sintering at 1750 deg C. Air sintering produced a limited region of solid solution in the stabilized zirconia portion of the system at 1450 deg C. Results on phase identification, oxidation behavior, and water corrosion are presented. (auth)

This report addresses the chemistry of hexachlorodigermane.

A critical comparison of measured and calculated central fission ratlos for 18 ZPR-III fast reactor assemblies was made with the object of examining the accuracy of computation of spectra and of the fission cross sections used. This comparison uses fission ratios measured with Kirn absolute fission chambers and computed with ANL cross section Set 635. The Kirn chambers and experimental technique are described. It is shown that ratios measured with threshold detectors must be corrected for the effects of inelastic scattering in the chamber walls. Possible sources of error in the experimental technique are discussed, and experimental evidence for the validity of the method is presented. The derivation of ANL Set 635 is described. It is shown that Set 635 is a modification of the Yiftah, Okrent, and Moldauer ANL Set 135 and that the central spectra and fission ratios calculated with the two sets are generally similar. The U/sup 234/and U/sup 236/ fission cross sections are not given in Sets 135 and 835; these were taken from ANL Set 179. The measured and calculated fission ratios obtained with U/sup 233/, U/sup 234/, U/sup 235/, U/sup 236/, Pu/sup 239/ , and Pu/sup 240/ were compared, both to search for trends …

A detailed design summary is presented for the Juggernaut, a water- cooled and -moderated thermal 250kw(th) reactor for neutron flux studies. Among the items discussed are the core, experimental facilities, instrumentation, etc. A cost analysis is given. (D.L.C.)

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 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)

S>A study was made of the kinetics and stoichiometry of the formation of hydrazoic acid in nitric acid solutions containing hydrazine and ferrous sulfamate. The data were used to establish safe limits for the use of hydrazine in process solutions. (auth)

S>A research program was completed on the composition limits for single- phase face-centered cubic crystal structures in the ZrO/sub 2/-rich region of UO/ sub 2/-CaO-- ZrO/sub 2/ and in the CeO/sub 2/-rich end of UO/sub 2/-- CeO/sub 2/, on the fabrication of highdensity pellets from these cubic compositions of both systems, on the properties of these cubic compositions, and on the irradiation stability of these compositions. Phase studies are reported that confirm the occurrence of cubic regions in both UO/sub 2/-- ZrO/sub 2/-- CaO and UO/sub 2/-- CeO/sub 2/. The properties measured include thermal conductivity, thermal performance testing, melting points, and corrosion in water and steam. Progress in the irradiation program is described. (D. L. C.)

Experimertal procedures are briefly described for the determination of the ratios of cross sections for the formation of isomeric states in nuclear reactions. Much avatlable experimertal data on isomeric yield ratios in nuclear reactions is compiled. Some of the collected data are discussed in terms of angular-momentum effects in nuclear reactions. (230 references).

The martensite burst transformation was studied in single crystals of iron containing 31.7% nickel. It was found that the morphology of the transformation was greatly simplified in crystals that had heen strained plastically prior to transformation. This simplification made possible detaiied crystallographic studies of the morphology of the transformation. These studies showed that the autocatalysis responsible for the burst transformation had its origin in a mechanical stimulation (coupling) between certain variants of the habit plane that were geometrically oriented such that the stress induced by transformation on one aided transformation on the others. In both strained and unstrained crystals, the most effective mechanical autocatalysis was observed to be between groups of four nearly parallel pianes whose poles clustered about common ( 110) directions. In the transformation of strained crystals, the operation of certain of these groups was favored. These were the groups whose planes were nearly perpendicular to the active slip plane, but did not include the group whose poles clustered about the Burger's vector of the active slip system. This behavior was taken to be a consequence of the anisotropic substructure introduced during deformation. Because of the enhanced transformation by certain groups in strained crystals, the frequency of secondary …

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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)

Calculational procedures oriented toward computer application are preserted to evaluate the neutron inelastic scattering cross section in the incoherent approximation for a simple cubic Bravais lattice. The differential scattering cross section, the scattering law, or inelastic scattering matrices and transport cross sections for multigroup calculations are evaluated using the contributions of 25 phonons. The inelastic scattering cross section for graphite is calculated as an example of polycrystalline media where the phonon-frequency distribution is dependent on the direction of polarization. (H.D.R.)

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.)

The Diffusion Kinetics codes described previously in ANL-6556 were used to study hypothetical reactions of free radicals produced by passing alpha rays and gamma rays through aqueous solutions. Tables and graphs of results are given for about 200 cases run on the IBM 704 with various parameter combinations. Intermediate as well as final concentrations are given for some gamma -ray cases. (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.)

BS>Descriptions are given of: (a) the design, construction, and adjustment of a Ford plane-strain compression die, to be used in the determination of constrained yield stress curves, and (b) the design and construction of a load cell with strain gages to be used in the measurement of the rolling load during rolling. (auth)

The swelling of U and of a few selected U alloys on postirradiation annealing was investigated by utilizing density measurements in conjunction with the observation of pores in the microstructures of annealed specimens. Speciniens were irradiated to about 0.3 at.% burnup in a constrained condition at approximately 275 deg C and were subsequently pulse annealed. The amount of swelling was found to be less than 1% for U specimens that were pulse annealed up to 75 hr at temperatures below 550 deg C; the amount of swelling, however, increased considerably on annealing at temperatures between 550 and 650 deg C. Specimens pulse annealed up to 75 hr at 618 deg C decreased in density by approximately 18%. The swelling was accompanied by the formation of bubbles on grain boundaries in recrystallized regions. The observations suggest that recrystallization is a necessary prerequisite for pronounced swelling in the alpha phase. Uranium specimens pulse annealed up to 75 hr at temperatures between 650 and 750 deg C in the BETA phase decreased in density by about 5%. Specimens annealed in the BETA phase, in contrast with those annealed at 618 deg C in the alpha phase, were badly cracked and contained pores of …

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