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This report addresses the advancements in nuclear propulsion for aeronautical system.

The deviation from the expected coolant flow distribution within the SNAP 2 reactor is due to the filling and draining of the unfed'' peripheral flow channels. An analysis of the cross-flow in a simulated SNAP 2 model omitting the unfed'' peripheral channels was made. The results of this investigation are presented herein. (auth)

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This report, for January 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Financial operations; facilities engineering; research; and employee relations. Weapons manufacturing operation; and safety and security.

This report, for February 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Financial operations; facilities engineering; research; and employee relations. Weapons manufacturing operation; and safety and security.

This, report, for October 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

This report addresses the comments of Westinghouse-Astronuclear Lunar Base Study.

The costs of the chemical and metallurgical steps in the fuel cycle for large desalination reactors are estimated. Both capital and operating costs are presented at varying plant capacities for a Zircaloy-clad fuel element containing depleted uranium and recycled plutonium as the oxides. UO/sup 2/-0.5% PuO/sub 2/. The chemical steps are reported at throughputs of 1, 10, and 30 short tons of uranium per day; and the metallurgical or fabrication step at throughputs of 1, 3, 5, and 10 tons per day, as specified by the Office of Science and Technology. The total estimated cost of all the chemical and metallurgical steps drops from .17 to .68 per kilogram of uranium as the cycle throughput is increased from 1 to 10 tons of uranium per day. All steps decrease in cost as plant capacity is increased, with the most impressive decrease in the irradiated assembly processing step, which decreases from .19 to 10 to 07 per kilogram of uranium as throughput is changed from 1 to 10 to 30 tons of uranium per day. The contained data in conjunction with previous studies of a natural uranium fuel cycle and results of a current reactor optimization study will yield complete fuel …

The smallmouth buffalo fish, Ictiobus bubalus (Rafinesque), population of Watts Bar Reservoir, of the Tennessee River down stream from Oak Ridge National Laboratory, was investigated in order to describe its age distribution, growth rates, dispersion, and importance as an accumulator of radionuclides. Measurements and scale samples were taken from commercially-caught fish and fish caught in the ORNL tagging operations. Scale impressions were anaiyzed for age and growth phenomena. Dispersion of smallmouth buffalo was investigated by conventional of ging methods and by autoradiographic analyses of scales. Stable and radiochemicsl composition of scales was examined by spectrographic analysis, flame spectrophotometer and radiometric surveys. Calcium was the most abundance element in fish scales with at lease twenty-three other elements present in varying quantities. Fish scaless and bone were found to contain radionuclides of ruthenium, cesium, zirconium, zinc, and cobalt. Radiometric surveys of scales revealed the Watts Bar Reservoir smallmouth buffalo population was a relatively minor accumulator of radionuclides with only 0.08 per cent showing the presence of artificially produced radionuclides. Approximately 6 per cent of the Clinch River fish and 77 per cent of the White Oak Creek fish had accumulations. Limited data on dispersion were determined from conventional tags. Much more dispersion …

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This report details activities of the Metallurgy Development Operation for the months of April, May, June 1964.

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Differential cross sections for elastic {pi}-p scattering have been measured at eight energies for positive pions and seven energies for negative pions. Energies ranged from 310 to 650 MeV. These measurements were made at the 3-BeV proton synchrotron at Saclay, France. A beam of pions from an internal BeO target was directed into a liquid hydrogen target. Fifty-one scintillation counters and a matrix-coincidence system were used to measure simultaneously elastic events at 21 angles and charged inelastic events at 78 {pi}-p angle pairs. Events were detected by a coincidence of pulses indicating the presence of an incident pion, scattered pion, and recoil proton and the results were stored in the memory of a pulse-height analyzer. Various corrections were applied to the data and a least-squares fit was made to the results at each energy. The form of the fitting function was a power series in the cosine of the center-of-mass angle of the scattered pion. Integration under the fitted curves gave values for the total elastic cross section. The importance of certain angular-momentum states, particularly the D{sub 13} state near 600 MeV, is discussed. Several possible explanations are given of the enhancement in the {pi}{sup -}-p cross sections near 600 …

Cemets are attractive as fuel for nuclear reactors because of their relatively high thermal conductivity and their apparent ability to withstand very high temperatures for prolonged periods of time. A number of cermet fuel specimens have been successfully irradiated at temperatures greater than 2000 C for periods of up to six weeks. Two cermet fuel plates described herein have successfully operated, in the snout facility, at {approximately}3000 C for four hours each. This continuation of the program for twelve more capsules is to investigate the diffusion characteristics of UO{sub 2} and fission products from the tungsten matrix and to study the dimensional stability of the system. The in-reactor test described in this report and in conjunction with extensive out-of-reactor studies will provide a firm basis for building cermet fuel technology.

The objective of the production test detailed in this report is to continue a program started under Production Test IP-690; the major change is an increase in sample enrichment. The higher enrichment is required to increase the portion of the fuel element core which is molten. This test will provide data to correlate maximum fuel temperature with post-irradiation microstructure, and data that are required to study the kinetics of fuel redistribution during the time interval between insertion of the capsule, into a constant, established neutron flux, and the time at which a steady state equilibrium structure is reached. This information will permit calculation of high temperature heat transfer coefficients and their variation during initial stages of irradiation. A quantitative understanding of fuel relocation and the time required to reach equilibrium are needed for optimum design of ultra-high temperature fuel elements.

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Purpose of this note is to recommend revised curves for the high-tank temperature required to maintain adequate high-tank backup support at the six small reactors. Compliance with the conditions shown on these curves will ensure adequate high-tank flow rates following the simultaneous loss of electric and steam power.

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