Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

The salt velocity technique for measuring coolant flow through a SNAP 8 tri-cusp channel was studied and developed. The parameters important in obtaining reproducible data were investigated and a test procedure, which yields dath of good precision, was developed. Dath were taken on a tri-cusp channel with flush circular electrodes (0.125 inch O.D.) as well as on a tri-cusp channel with parallel plate electrodes (0.006 inches thick, 0.250 inches long), which were situated 0.050 inches apart and protruded 0.040 inches into the stream. The data are presented as the ratio of U/sub exp//U/sub avg/ where U/sub avg/ is calculated by means of a flowrator and channel geometry. It was found that in the tri-cusp channel for a range of Reynolds Numbers of 11,000 to 25,000, a radial velocity profile could not be sensed. The peripheral velocity profile over the central baif of the cbannel appeared to be flat and relatively.independent of the Reynolds Number. The data were compared with similar work of Palmer and Swanson in a qualitative and quantitative manner. Reasons are given for using a single calibration factor in the hydraulic model testing of S8DS core. While some slight modifications should be made to further improve the accuracy …

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This document details activities of the irradiation processing department during the month of October, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

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(VSR = vertical safety rod.) This report summarizes results of development programs which have evaluated vertical rod channel sleeving materials and provided flexible vertical rods, acceptable for both interim use before rod channel sleeving, and for subsequent use in sleeved channels. B{sub 4}C is the rod material; graphite and Al oxide are among the sleeve materials.

A procedure is described for the activation determination of V in powdered milk using 3.77-min V/sup 52/. The quantity of V in the sample is obtained by comparing the V/sup 52/ radioactivity found in the test sample with the V/sup 52/ radioactivity in a V comparator sample that is treated in the same manner as the test sample. The procedure can also be used for the determination of V in a variety of materials. (P.C.H.)

The design and performance of SRE Core II fuel elements, moderator cans, hot traps, cold traps, control elements, pumps, main primary heat exchanger, valves and sodium piping, and instrumentation are discussed. (R.E.U.)

The following analysis of the induced radioactivity in SNAP-50/SPUR electrical machinery having a high cobalt content is submitted. Induced radioactivity in the flight vehicle will contribute negligibly to allowable radiation levels. This is especially so due to the low neutron to gamma ratio of assumed radiation damage tolerances to semiconductors. A calculation to estimate the order of magnitude of induced radioactivity in cobalt is attached. The calculation is based on a best guess of the neutron spectrum directly behind a lithium hydride shield. The resulting low cobalt activity and associated dose rate of about 1 mr/hr at 10 ft from a generator or a motor is insignificant. Although the evaluation indicates insignificant levels of induced radioactivity, this conclusion is not applicable to a ground test. Neutron moderation and scattering from a containment vessel and biological shield would greatly perturb the neutron environment behind the flight shield. Posttest handling of all components within the vacuum test chamber will undoubtedly be a problem. Notwithstanding the importance of limiting induced radioactivity, other considerations such as economy, cooling and vacuum requirements will largely dictate the final facility design. In summary, an activation analysis involves the overall facility design and will not be readily resolved. …

An investigation was conducted on the impossible use of beta radiation to promote chemical reactions at high temperatures and pressures. The advantages of beta sources over other radiation sources are enumerated. A radiation processing apparatus is described which allows operations to 10,000 psi and 500 deg C and uses 90 C of Sr/sup 90/-Y/sup 90/. The dosimetry of the source was accomplished with an iodineheptane system, and the mean dose rate within the chemical reactor was determined to be 0.98 x 10/sup 6/ rad/hr. The radiation utilization efficiency in the dosimetry measurements was determined to be 34.7%. Results of runs on hydrogenation of coal extract indicate that radiation does not increase the extent of hydrogenation, but that radiation reduces the content of hetero atoms N and S in the 100 x 400 deg C boiling oil products. The use of beta radiation in the hydrorefining of oils is suggested. (D.L.C.)

The Control Drum Actuator Checker is used to verify the operation of the hydraulic control drum actuators before they are installed on the reactor. It provides for local checkout after installation. It provides for local checkout after installation. It also provides for pre-installation hydraulic leak and pneumatic seal test on individual actuator assemblies.

This is the monthly report for the Hanford Laboratories Operation, October 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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Research and development progress is reported on BORAX-V, fast-reactor physics, fast-reactor fuel, EBRII, FARET, applied nuclear physics, theoretical nuclear physics, reactor fuels, reactor materials, metallurgy alpha - gamma hot cell, heat engineering research, chemical separations, plutonium recycle program, magnetohydrodynamics, rocket fuel test reactor, nuclear safety, and TREAT. (M.C.G.)