Using the Berkeley polarized-proton target, we have measured the polarization parameter P({theta}) for proton-proton (p-p) scattering. The measurements were obtained at beam kinetic energies of 0.330, 0.680, and 0.740 GeV at the 184-in. synchrocyclotron and 1.70, 2.85, 3.50, 4.00, 5.05, and 6.15 GeV at the Bevatron. The angular regions measured were from 20 to 100 degrees center of mass; the square of the four-momentum transfer ranged from 0.1 to 0.8 (GeV/c){sup 2}.

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Tube life estimates for the base case and the five study cases are given for 6.6 and 7.0 pH. The fuel sizes and operating conditions for each case are summarized. Information on the mixer position that gives maximum tube life for each case is shown. A tube life distribution was calculated for the base case using the outlet temperature distribution for 1197 central zone tubes at B reactor. Average tube life for the 1197 tubes war estimated to be 3.0 years (100 percent TOE) for operation at 6.6 pH, and the outlet temperature corresponding to average tube life vas l07{degree}C. Similar numbers could be calculated for the study cases if estimates of the outlet temperature distributions were available.

In 1961, large-size, smooth-bore, Zircaloy process tubes were installed in C-Reactor graphite channels that had been enlarged to 2.275 inches. These tubes were installed to provide a test and demonstration facility for the concept of overboring as a means of securing significant improvement in the production capability of the reactors, After two years of facility operation, it is now appropriate to consider the extent to which original objectives have been achieved, to re-examine the original objectives, and to consider the best future use of this unique facility. This report presents the general results of such a review and re-examination in more detail.

The objective of this test is to evaluate the effects of oil quenching, alpha annealing, and an Al-Si braze pre-canning treatment on the irradiation behavior of hot-die-sized fuel elements.

This report describes a study which was made to determine possible changes in mixer placement at H reactor because of the change from an enriched core load to a natural load and to evaluate movement of metal charges 8 inches downstream. Also studied was the effect of short charging on tube life and mixer position. Special consideration was given to the fact that H reactor will shut down in approximately seven months.

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To assure that the NEERVA reactor will function reliably during its test program, cleanliness must be controlled at each stage. These stages include design, manufacture, assembly, shipping, and test. The assembly stage is that phase which this handbook is concerned.

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In the first of a series of experiments performed to investigate the protection afforded by various typical structures against prompt weapons radiation, radiationintensity measurements were made at the Tower Shielding Facility in two concrete-shielded bunkers and in an interconnecting tunnel. Prompt weapons radiation was simulated by the Tower Shielding Reactor II, which was operated 100 ft above the ground. The distance between the reactor and the bunkers was approximately 700 ft. The bunkers were each 12-ft cubes and were constructed so that the shield thickness on the front face of one and on the top face of the other could be varied in 4-in. steps from 0 to 20 in. The thickness of concrete and dirt surrounding all other faces was sufficient to make them black to incident radiation. The immediate goals of the experiment were to study (1) the attenuation of radiations by various thicknesses of ordinary concrete slabs, (2) the buildup of radiation intensities within the cavities by scattering of radiation in the walls, and (3) the transmission of radiation down a tunnel with two right-angle bends. The gamma-ray and fastneutron dose rates and thermal- neutron fluxes measured at various positions within the bunkers and in the tunnel …

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Using the straight-ahead approximation, nucleon-meson cascade calculations were carried out for several solarflare proton spectra incident on a shield. The shield material has approximately the properties of aluminum. Both spherical-shell and slab geometries are considered. (auth)

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