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This document details activities of the Hanford Atomic Products Operation (HAPO) during 1954.

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This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this program, it is estimated that 1650-2350 megawatts of total additional production will be achieved.

This document from Savannah River Plant reports progress for June 1955 in the 100, 200, 300, and 400 Areas. Information is presented on the assembly area, reactor control, reactor complex, and disassembly for the 100 Area (reactors). From the 200 Area (separations plants), progress at the solvent extraction plants is reported. Uranium - Aluminium and thorium canning are reported for the 300 area (reactor fuels fabrication). And stainless steel corrosion studies are reported for the 400 area (heavy water).

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Study approvals are listed for Studies 8506, 8509, 8518, 8519, and 8520 with man-months and program dates specified. Safety and security agreements are listed. Additional topics discussed are: financial status, experimental physics programs, pile engineering division program, and technical division study status.

Study approvals are listed with man-months and date specified. Information and safety agreements were reached. Occupational safety and radiation protection, fuel slug development, instrumentation, ingot rolling, and security violations are discussed topics. Appendices contain information on financial status, pile materials program, instrument development program, and technical division study status. (GHH)

Nine technical studies were approved for funding. Discussions at the meeting centered around safety and work schedules. Appendices contain information on Financial status, the Separations program, the Analytical Chemistry program, and the Technical Division studies that were approved at the meeting.

This document is the April 1955 Monthly Report of the Process Section/Manufacturing Division at the Savannah River Plant. It contains information on activities in each of the SRP areas (100-400 areas), as well as on utilities and general services.

This document is the July 1955 Monthly Report of the Process Section/Manufacturing Division at the Savannah River Plant. It contains information on activities in each of the SRP areas (100-400 areas), as well as on utilities and general services.

This document has been written because of a request for information from the Advisory Committee on Reactor Safeguards. Hanford operating experience has been summarized in terms of operating hours, startups and scram analysis.

Nuclear parameter variations are presented for sodium graphite reactors using Pu-spiked natural U as fuel. The fuel feed is assumed to be natural U, and the important variables are the initial amount of excess reactivity, lattice spacing, and alpha , the ratio of Pu/sup 239/ to U/sup 235/ in the feed material. The system is called "steady state" in that the ratios, N/sub 40/N/sub 49/ = sigma /sub c(49)// sigma /sub a(40)/ and N/sub 41//N/sub 4 9/ = sigma /sub c(49)/ / sigma /sub a(41)/, obtained from setting the build-up equations to zero are assumed for the feed concentrations, and the feed material to the reactor is always the same. During irradiation, the U/sup 235/ and U/sup 238/ concentrations steadily decline while the Pu isotope concentrations initially increase, then decline. To ensure sufficient plutonium for feed material, it is necessary to remove the fuel from the reactor before the Pu content drops below its initial value. Although the reactivity variations presented were calculated specifically for sodium graphite reactors, they may be applied to any thermal reactor using Pu-spiked natural U as fuel. The reactivity changes are determined primarily by the fuel characteristics and are only slightly dependent on the other …

Major additions to separations facilities may be required because of increased reactor power levels, reduced exposures; changes in slug specifications, obsolescence of existing solvent extraction plants or development of new separations processes with lower operating costs. The magnitude of first costs for a separations plant is so large as to discourage production planning which would require an additional major separations facility. Experience in separations design has shown that certain process and equipment changes, if they could be developed, would significantly reduce the capital investment in a separations facility. Accordingly design development for a new separations facility is under way. The purposes of this document are to present the results of the first separation design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve significant capital and operating cost reduction.

One uranium tensile specimen irradiated to 620 MWD/T (1.75 x 10{sup 20} nvt) was tested at 285 C (545 F). The values obtained were: ultimate tensile strength 71,000 psi, 0.1% offset yield strength 70,000 psi, percent elongation (one inch gage length) 0.7, and modulus of elasticity 12 x 10{sup 6}. These values are comparable to the as-irradiated values of specimens tested at room temperature which were: ultimate tensile strength 76,000 psi, 0.1% offset yield strength 71,500 psi, and percent elongation (one inch gage length) 0.36. The elongation of the specimen tested at 285 C was less than that of a specimen annealed at 700 C (1290 F) after irradiation, then tested at room temperature. Experiments have been initiated to determine the structural stability of irradiated uranium-silicon alloy when this alloy is in the stable epsilon phase. Present work is limited to the evaluation of thermal expansion as a criterion for degree of epsilonization. This technique has not proven satisfactory. The damage resulting from the bombardment of uranium with electrons in the 1-2 MEV range is to be evaluated using electrical resistivity and x-ray diffraction to determine the extent of the damage. Calculations indicate a threshold energy of about 1.25 MEV …

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This report summarizes work completed during the Redox Plant shutdown in January 1955. An analysis of major difficulties encountered, improvements made during the shutdown, and building design deficiencies brought to light by the shutdown are discussed. (JL)

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This report presents details of the operations of the Savannah River Plant manufacturing division during the month of February 1955.

This report presents the details of the operation of the Savannah River Plant manufacturing division during the month of May 1955.