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The effect of radiation on the superconducting transition temperature (T/ sub c/), upper critical field (H/sub c2/), and volume-pinning-force density (F/ sub p/) were discussed for the three kinds of superconducting material (elements, alloys, and compounds). 11 figures, 3 tables, 86 references. (auth)

This report describes the derivation of three groups of equations: (1) Field components from an arbitrarily shaped filament lying in a plane. (2) Field components from an arbitrarily shaped ribbon of infinitesimal thickness with center line lying in a plane. (3) Field components from an arbitrarily shaped bar of rectangular cross section with its center line lying in a plane. In all three cases analytical expressions for the field components were found for an infinitesimal element of the cross section. These expressions are then integrated numerically along the arbitrarily shaped center line of the coil to obtain the three field components. As a check for accuracy the calculated field values of an elliptically shaped coil were compared to an existing analytic expression for a filamentary elliptical coil. (auth)

A method for giving quantum mechanical meaning to particle-like (soliton) classical solutions is described in an attempt to relate particle-like solutions of classical nonlinear field theory to physical hadrons. The method uses the familiar canonical Hilbert space formalism of quantum mechanics and has been applied to the quantum mechanical interpretation of both static and time- dependent classical soliton solutions. (SDF)

A brief summary of the scope of HSST projects is presented. A major emphasis throughout the course of this work is the verification of methods of fracture prediction which can be utilized in an assessment of pressure vessel integrity. The utility of small specimens which are appropriate for surveillance purposes continues to be investigated in both the unirradiated and post- irradiated conditions. 11 references (auth)

The high strain rate tensile properties of annealed 2$sup 1$/$sub 4$ Cr- 1 Mo steel were determined and the tensile behavior from 25 to 566$sup 0$C and strain rates of 2.67 x 10$sup -6$ to 144/s were described. Above 0.1/s at 25$sup 0$C, both the yield stress and the ultimate tensile strength increased rapidly with increasing strain rate. As the temperature was increased, a dynamic strain aging peak appeared in the ultimate tensile strength-temperature curves. The peak height was a maximum at about 350$sup 0$C and 2.67 x 10$sup -6$/s. With increasing strain rate, a peak of decreased height occurred at progressively higher temperatures. The major effect of strain rate on ductility occurred at elevated temperatures, where a decrease in strain rate caused an increase in total elongation and reduction in area. (auth)

Experimentally determined neutron cross sections, resonance parameters, and the average number of neutrons per fission for neutron-induced fission of actinide nuclides in the production chains associated with thermal and near- thermal reactors are summarized and compared with user requests for experimental data. The primary fertile and fissile isotopes $sup 232$Th, $sup 233$U, $sup 235$U, $sup 238$U, and $sup 239$Pu are excluded from this survey. Integral data, i.e., spectrum-averaged thermal cross sections and resonance integrals, are included, but the emphasis is placed on energy-dependent differential cross sections because of their general utility with any specified neutron energy spectrum. Included with the data summaries are an extensive survey of the literature through August 1975, brief descriptions of measurements known to be in progress or firmly planned for the immediate future, and recommendations for needed measurements. (3 figures, 5 tables) (auth)

Topics discussed are: aquatic effects of thermal electric power stations; legal aspects of water pollution; EPA provisions for levels of thermal discharges to assure protection and propagation of a balanced, indigenous population of shellfish, fish, and wildlife in a body of water; cost benefit analysis of steam electric power effluents; cooling systems and siting of power plants; simulation modeling of population dynamics; and sociological aspects of water pollution. (HLW)

A technique for making metal ions for cyclotrons is described. Metal and non-metal ions from solids are produced in a Penning ion source by a process that involves ions that are unable to cross the first acceleration gap between the ion source and dee and are accelerated back into the ion source where they sputter charge material into the arc. This material is ionized and extracted from the ion source and accelerated. This technique was used for a large variety of ions, both metal and non-metal, including aluminum from the metal and boron from boron nitride charge materials. The efficiency for making iron ions with different ion support gases was calculated, and these results were experimentally checked. A dual ion source is being designed for a dc Penning ion source test stand which makes an excellent source for producing ions from solids for dc extracted Penning ion sources. (auth)

In an earlier paper Schoenborn, Caspar, and Kammerer (J. Appl. Cryst. 7, 508-10(1974)) reported the fabrication of thin film monochromators for neutrons. They showed that a multilayer consisting of alternating films of two materials acts as a good monochromator with large and adjustable periodicity and wide bandwidth. The diffraction properties of these multilayers have been studied with the objective of using them as monochromators, filters and polarizers for neutrons. A theoretical understanding of these multilayers has been developed by using the kinematical and dynamical approaches. In order to compare these expressions with the observed properties, the effects of beam divergence and wavelength distribution for the spectrometer have been determined. The influence of some aperiodicity on the diffraction data has also been studied within the framework of kinematical theory. (auth)

The DMA10 is a high speed link between a PDP-10 and up to eight PDP-11s; specifically, the PDP-10 shares sections of its memory with the PDP-11s. The two segment concept on the PDP-10 of shared/reentrant code and non-shared code is implemented. The inclusion of read only memory on the PDP-11s allows for the development of ''PROM'' software which all the PDP-11s may share. The principal difference between the DMA10 and other communications interfaces is that it is not a block transfer device. Because of the shared memory concept the features of the DMA10 are high data bandwidth and minimal processor intervention between data transfers. Communication programs between the PDP-10 and the PDP-11 may be tested wholly in either processor, independent of the DMA10 interface. In the current mode of operation the PDP-11's simply act as device controllers. Future plans include separate operating systems in various PDP-11s. (auth)

A review of data and information on radiation damage in nonmetallic solids is presented. Discussions are included on defects in nonmetals, radiation damage processes in nonmetals, electronic damage processes, physical damage processes, atomic displacement, photochemical damage processes, and ion implantation. (JRD)

A review of the various nuclear models used in the evaluation of neutron nuclear data for fission and fusion reactors is presented. Computer codes embodying the principles of the relevant nuclear models are compared with each other and with experimental data. The regions of validity and limitations of the conceptual formalisms are also included, along with the effects of the numerical procedures used in the codes themselves. Conclusions and recommendations for future demands are outlined.15 tables, 15 figures, 90 references. (auth)

Computer models are used to simulate both localized and extensive thermal excursions in a large superconducting magnet for fusion reactor. Conditions for the failure of fusion magnet due to thermal excursion are delineated. Designs to protect the magnet against such thermal excursion are evaluated. (auth)

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The automated absolute activation analysis technique developed at the Savannah River Laboratory is based on the ability to predict neutron capture reaction rates from tabulated cross sections and neutron spectra accurately calculated for the 100-mg $sup 252$Cf source. A series of computer programs comprises the data reduction system which: (1) reduces the gamma-ray spectra to lists of photopeak energies, areas, and statistical errors for all significant photopeaks, (2) assigns each gamma ray to the appropriate activation product by comparing experimental to tabulated gamma-ray energy, (3) converts each photopeak area into an elemental concentration using the experimental timing data, calculated reaction rates, detector efficiency, and activation product spectroscopic data in the absolute activation master equation. The data reduction system requires about one second of IBM 360-195 CPU time for the conversion of each 4096 channel spectrum into a qualitative and quantitative list of elemental composition. The accuracy of the algorithm is better than +- 15 percent for most elements. (auth)

Measurements of polarization of the non-characteristic x-radiation emitted from collisions between energetic (10--90 MeV) Al ions in thin foils are presented. 2 figs (GHT)

Vertical slip flow and flooding models, which have been incorporated in a version of the RELAP4 computer code by Aerojet Nuclear Company have led to significant improvements in modeling nuclear reactor coolant system phenomena during postulated large and small break loss-of-coolant accidents. The vertical slip flow model computes the separated fluid component velocities and directions at vertical flow junctions. Use of the slip model allows the energy transfer between volumes to be based on individual liquid and vapor component flows rather than on the net junction flow. Continuity and momentum equations are unaffected by the addition of slip. The vertical flow slip model logic is based on the assumption that gravity forces dominate causing slip between phases. 7 references (auth)

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The statistical theory of average neutron nucleus reaction cross sections is reviewed with emphasis on the justification of the Hauser Feshbach formula and its modifications for situations including isolated compound nucleus resonances, overlapping and interfering resonances, the competition of compound and direct reactions, and continuous treatment of residual nuclear states. 3 figures. (auth)

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Radio-frequency signals simulating electrical interference ranging from 50 Hz to 50 MHz were applied to the shields of the input cable system (two solid- shielded, mineral-insulated cables approximately 6 m long) of a wide-band (approximately 60 MHz) differential preamplifier for use with fission counters as input devices as part of in-vessel, low-level flux monitors in future liquid- metal fast breeder reactors (LMFBRs) to determine the common-mode rejection. Results show that differences in electrical properties and shielding characteristics of the two input coaxial cables along with end effects produced by an unbalanced sensor severely degrade the rejection capability of the differential preamplifier. At 1 MHz, the common-mode rejection without input cables is approximately -70 dB; this is reduced to approximately -10 dB when measured with the rf signal applied to the surface of the input cable shields. Measurements of the shielding characteristics of the input cables showed resonances at test frequencies greater than 2 MHz. A ferrite core was installed in the input assembly to increase the impedance of the shields and to permit termination of the coaxial line consisting of the input cable shields and the protective metal conduit for the input cables. This assembly eliminated all resonances below 20 …

Suitable fuel forms for radioisotopic thermoelectric generators are granules of high internal density (greater than 95 percent of theoretical) or geometric shapes (80 to 90 percent dense) such as pellets or spheres. Both forms can be made from calcined $sup 238$Pu(III) oxalate. The conditions for processing PuO$sub 2$ are controlled during fuel form fabrication to ensure pellet integrity; to control density, grain size, and porosity distribution; and to minimize the fraction of potentially respirable fines. The competing phenomena of expansion caused by radiation damage (including helium generation from radioactive decay of plutonium) and shrinkage caused by sintering must be controlled to assure dimensional stability. The variation of microstructure and related physical properties with process parameters is discussed. (auth)

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