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The purpose of this document is to update 190-C pump capacity information previous released in HW-52449{sup 1} and HW-58580{sup 2}. Improvements in motor cooling has resulted in raising the previous 3500 HP limit to 3660 HP{sup 3} thus increasing total pumping capacity.

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The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

Uncontrolled boiling of the water in a process tube might result in serious damage to a pile. Consequently, it is desirable to maintain header pressure generally sufficient to sweep out any steam which might be formed. Since the header pressure required to remove the steam depends upon the power output of the tube, the power level of a tube or pile is limited by the pressure available. In the past, tube power limitations have been specified and interpretations thereof. Recently a through study, both theoratical and experimental, has been made to determine the validity of these limitations. The purpose of this report is to present the results of the study must make recommendations for future operations. The limits presented herein are based on tube power levels.

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This report, for July 1957 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 for June 1958, 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, for August 1958 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operation; facilities engineering; research; and employee relations.

Two new production records were set during April, for processed U and Pu production. 0.9 tons sheared NRX fuel were dissolved in Redox. Discrepancies in Pu yield are being studied. Alternate methods of recovering Np are being evaluated. The Purex prototype facility will be converted to the anion exchange process. Alternate designs for a Purex miniature service dissolver were reviewed. The Purex HA column will be replaced.

The September, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

The July, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

Purex and Redox plants operated satisfactorily. Pu production exceeded commitments. The continuous calciners in UO{sub 3} plant experienced difficulty, but the monthly commitment was exceeded. Capital costs for conversion of B plant to recover Cs and Ce have increased. For future processing of E metal, several 3-ton batches were dissolved in Redox. The continuous Task I prototype is being tested for startup of production facilities. Redox product solutions generally have higher waste losses than these from Purex material. The continuous anion exchange prototype will also be tested. Engineering studies were completed of two facets of Purex Phase II expansion, plant conversion to two cycles, and expansion to a rate of 25.8 tons U/day. A proposal requests authority to expand Purex to capacity factor 3.2 along with the two-cycle conversion. The Pu trifluoride process review indicated that conversion to the PuF3 process is not likely. Separations plant dissolver capacity potential for the next 5 yr was studied. (DLC)

Production of Pu from separations plants and output of unfabricated Pu exceeded commitments. Purex plant set a new record high for U processed. Production and shipments of UO{sub 3} met schedules. Purex solvent extraction battery performed below normal, probably because of poor solvent quality. NaOH addition to Redox coating removal waste is being reduced. A 3fold improvement in Recuplex product Al impurity was achieved by means of a specific gravity difference > 0.15 between dilute aqueous feed and extractant. Sintered, high-silica crucibles are being tested in RMA production line in Finished Products Operation. Scope design of a fission product shipping cask was completed; powder temperature should be below 440 F for 1 MCi cerium-144 + impurities. Feasibility of using one outside Purex canyon entrance (stairwell opening) for relief damper opening was tested and found to be insufficient. A drawing of the 6-inch continuous centrifuge being evaluated as a vacuum drum filter on RMA button line was reviewed. Casks were designed for the NPR project. (DLC)

Record highs were set for Pu output in separations plants and for amount of U processed in Purex. UO{sub 3} production and shipments exceeded schedules. Fabrication of 200 and 250 Model assemblies is reported. Unfabricated Pu production was 8.5% short. Nitric acid recovery in Purex and Redox is reported. Prototype anion exchange system for Pu was tested in Purex. Hinged agitator arms with shear pin feature was installed in UO{sub 3} plant H calciner. Operation of continuous type Task I, II facility improved. DBBP is considered for Recuplex. Methods for Pu in product solutions agreed to within 0. 10%. Purex recycle dock shelter is complete. Other projects are reported.

The September, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.

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A compilation of available data on the spectra of thorium is presented, including energy levels and classified lines with Zeeman effects and isotope shifts, as well as certain data on unclassified lines. The present status of knowledge of these spectra is discussed. (auth)