This is the monthly report for the Hanford Laboratories Operation, July 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities,, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This document details activities of the irradiation processing department during the month of June 1960. 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; employee relations operation; and financial operation.

This monthly report details reactor and materials technology activities during the month of June 1965.

Submitted herewith are source and special nuclear material composition for the month of June, 1966. Normal uranium, depleted uranium, enriched uranium, plutonium, thorium, uranium-233, deuterium, enriched lithium, neptunium-237, plutonium-238, and tritium are accounted.

This report details activities of the Fuels Development Operation for the months of April, May, and June 1961.

The program`s objective is to develop the technical foundation for use of projection fuel elements through an accelerated testing program. Two types of projection fuel elements are being considered (1) Self-supported fuel elements for use in ribless aluminum or zirconium process tubes; and (2) Bumper fuel elements for use in ribbed process tubes. A further objective of the program is to determine the most desirable method of fabrication and type of support for projection fuel elements. The program must develop the self-supported concept in time to meet the proposed ribless zirconium process tube installation schedule. Parallel development of the bumper fuel element is an interim program to realize immediate gains in reduced hot spot rupture tendency, during the change over to zirconium tubes. The appended charts indicate the proposed accelerated testing and development schedules being followed. Testing of the self-support concept has indicated that the collapsible supports are adequate to maintain fuel centering, do not introduce additional corrosion problems resulting from the supports, and do in fact greatly reduce the incidence of hot-spot flow patterns. Reductions in rupture potential of at least a factor of 30 have been demonstrated at the 95% confidence level. Bumper fuel testing has indicated that …

The monthly report for the Hanford Laboratories Operation, June 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

The demonstrated operating efficiency performance which has resulted from poison spline usage forces an economic decision concerning the self-supported and bumper fuel element programs. As originally conceived the projection fuel elements would preclude the insertion of a spline under the fuel charge; thus it is very important that means be devised either to make poison spline usage compatible with future pile loadings or to demonstrate that some other supplementary control system, which is compatible with future pile loadings, can approximate the effect the splines have an operating efficiency. This report shows the appreciable performance improvement which has been achieved at KE Reactor through the application of the poison spline system.

This document details activities of the irradiation processing department during the month of June, 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.

This document details activities of the Irradiation Processing Department during the month of June, 1964. 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; Employee Relations Operation; and Financial Operation.

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

The initial physics tests on the Shield Test Experiment reactor and the precriticality rod-drop test data are presented. (auth)

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Fabrication of internal reflector pieces for the SNAP-8 core is described. These reflectors were made of BeO, with and without the addition of Sm/sub 2/O/sub 3/ as a nuclear poison. Because of the high density and dimensional tolerance requirements, the complexity of shapes, and the comparatively modest number of parts to be produced (approximately 1000), the blanks were hot pressed and subsequently machined with diamond wheels and cores. In almost all cases, the specified density of 98% of theoretical was achieved. The low eutectic temperature in the BeO--Sm/sub 2/O/sub 3/ system of about 1420 deg C necessitated special pressing parameters, which were arrived at by experimentation. A rather coarse grit size (80) was used for the diamond wheels, which resulted in very little wear to the wheels, and an extremely low dimensional rejection rate on the blanks. Because of the toxicity of BeO, all equipment was enclosed, and was held under negative pressure. (auth)

ABS>Research and development progress is reported on water-cooled reactors, liquid metal-cooled reactors, general reactor technology, plutonium recycle, advance systems research and development, and nuclear safety. Topics covered include the EBWR, BORAX-V, EBR-I, EBR-II, FARET, applied reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering and fluid flow, chemical separations, Argonne Advanced Research Reactor, subcritical reactor as substitute for isotope sources, thermal reactor safety studies, fast reactor safety studies, and direct conversion studies. (M.C.G)

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A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)

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The thermal-neutron fluxes in the lattice positions and selected experimental positions of the ETR were measured for Cycle 51B. Gamma heat generation was also measured in various experimental positions for Cycles 51B and 54. Vertical traverses for each position monitored are shown. (auth)

The theoretical development, statistical treatment, and application of hot channel factors in compact SNAP reactors as represented by the SNAP 8 experimental core loading are presented. The channel and rod power effects of variation in the concentrations of uranium, hydrogen, and poison in the fuel rods are given. The statistical distributions of all variables are examined. A random selection of rods and channels is compared to the actual SNAP 8 configuration, with no difference noted. Confidence limits are set on hot rod and hot channel factors. Various other factors and aspects of the problem are discussed. The results of the study showed that the hot channel factors may be reduced to less than +2% over the nominal power, as opposed to a hot channel factor of about +10% as previously determined by empirical methods. (auth)

This report addresses the progress report of the advanced thermoeletric development program during February 1966 to April 1966.

This report addresses a progress report of the advanced thermo-electric development program.