From Introduction: "The principal objective of this investigation is to promote fundamental understanding of the mechanism of solidification of aqueous solutions, and the effects of externally applied electrical and magnetic fields on solidification."

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The tissue dose calculations of Kinney were used to calculate several importance functions associated with the dose from primary and secondary particles in the tissue due to penetration of an aluminum shield by a solar-flare proton spectrum. Secondary particles produced in the shield were not considered. (auth)

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A FORTRAN II program is described for utilizing cross section data for spallation products to obtain an estimate of the residual radiation from the bombardment of materials with high-energy particles. The program listing is included, together with sample input and output. (auth)

Declassified 6 Sep 1973. Results of the parametric study are given for both present and advanced capability (2 and 8 MW). Fuels which result in minimum reactor weights are UC/UN (95% dense), UC/UN--1W for the 2 MW design, UC/ UN-1W for 8 MW. Effects of fuel clad and fuel maximum temperature on the reactor weight were also studied. Recommendations are made for the 2-MW SNAP-50/ SPUR fuel element development and reactor design program, and for additional parametric studies. (DLC)

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This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.

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The conclusions are: (1) The formation of powder or ``oxide`` in the storage container is caused almost entirely by packaging of plutonium in plastic materials. (2) The corrosion of the plutonium follows degradation of the plastic due to the intense radiation. (3) The powder, formed by this corrosion is not PuO{sub 2} but a mixture of oxides, hydrides, and chlorides in varying proportions, depending on the type and amount of plastic in the individual storage container. (4) The powder consists predominantly of hydrides. Hydrogen is considered the major cause of severe corrosion. The surface-disruptive nature of hydriding prevents formation of any protective film on the metal. Fresh surface is provided continuously for further attack. (5) The hydrides are pyrophoric. Spontaneous ignition of the powder and metal occurs occasionally, immediately following opening of the container. This effect may be more severe for ingots than for buttons because of unreacted- or only partially-reacted metal fines in the powder from ingots. (6) Metal loss of eight percent in 100 days of storage has been observed for unalloyed ingot metal of moderate purity under the storage conditions described in this report. Corrosion rate depends on purity of the metal. Impurities in unalloyed metal inhibit …

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Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1963 activities, finance, public relations, honors, service, organizational leadership, and other information about scouting programs.

Abstract: A materials exposure program has been established in the Garigliano Nuclear Power Plant to measure the effect of neutron irradiation and time at temperate on the mechanical properties of the reactor pressure vessel steel. Base metal specimens were made from portions of the pressure vessel steel, and weld heat-affected zone and weld metal samples were taken from a weldment made from the pressure vessel steel and simulating a pressure vessel circumferential weld since there are no longitudinal welds in the forged ring shell. The specimens were sealed in helium-filled capsules and placed in the reactor vessel at locations where they will be exposed to a variety of conditions. Tensile property changes will be measured by pre- and post-irradiation tests on small tensile specimens. Fracture characteristic changes will be measured in similar fashion by Charpy V-notch impact tests. The program is planned to cover a 32-year period, with specimens to be removed for test at intervals of 1, 2, 4, 8, 16, and 32 years.

A listing of the data on the revised tape is presented. The nuclear data are a reproduction of the computer printout. Other nuclear data (spectra, energy, absorption cross section of some poisons and absorption and fission cross sections of selected fuel materials) were transcribed from the tape listing to provide a more compact format or to allow easier comparison of absorbers and fuels. (auth)

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The development of processes to separate and purify the transuranium elements, process equipment development, HFIR target fabrication studies, design of the TRU Processing Plant, design and installation of development facilities, corrosion studies, and analytical research directed toward this program are reponted in 6 papers. Separate abstracts were prepared for each paper. (M.C.G.)

From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.

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Fast neutron and gamma-dose rates within 4-ft-dia., 20-ft-deep, concrete- lined holes were measured at the Tower Shielding Facility. The radiation source was the Tower Shielding Reactor II (TSR-II) enclosed in a shield that modified the neutron to gamma ratio of the reactor leakage spectrum to more closely resemble that of a weapon spectrum. The holes were located at horizontal distances of 100, 228, and 450 ft from the reactor. From the hole at 100 ft extended a reinforced concrete-lined tunnel, 6 ft high, 21/2 ft wide, and 20 ft long, with its ceiling 10 ft below ground level. The experimental measurements consisted of vertical traverses in the three holes and horizontal traverses in the tunnel. The parameters varied included distance from the reactor, the angle of elevation of the reactor with respect to the horizontal at the hole, and the material and thickness of the shield over the hole. Reactor elevation angles ranged from 15 to 90 deg . The shields over the holes were concrete, iron, and laminated iron and concrete slabs. (auth)