This document details activities of the irradiation processing department during the month of March, 1957. 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 document details activities of the irradiation processing department during the month of July, 1957. 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.

The description and development, selection and descriptions of processes, design, and specialized design problems are presented for the 400-D Area at the Savannah River Plant. These facilities were used for the production of high purity heavy water for use as a moderator and coolant in the 100 Areas. Also, deuterium gas and hydrogen sulfide were produced here.

The December, 1956 monthly report for the Chemical Processing Department of 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 operations. (MB)

This report discusses five Reactor (100) Areas constructed at SRP. They were designated as 100-C, K, L, P and R. A minimum distance of two miles separated any two of the areas which were laid out in the form of a semi-circle, Each area contained approximately 40 permanent buildings and facilities for a total of 200 buildings for all of the 100 Areas. Construction was started on the R Area first and this was the first area to be completed and accepted by Operations. Construction of the other areas was started and completed in the following sequence: P, L, K and C. The difference in the design and construction of the various facilities in these areas is noted under the individual building discussion on the following pages of this section of the Construction History and also in the du Pont Engineering and Design History. In the series of manufacturing operations the separation of fissionable materials produced in the 100 Areas is accomplished by chemical and physical means in the 200 Areas These are the 200-F and 200-H Areas which have duplicate facilities in the process phase. However, a central laboratory, area shops, laundry, metallurgical and storage magazine buildings were constructed …

This report details activities of the irradiation department during the month of September, 1957. The report is divided into the following sections: Research and Engineering operations; Production and Reactor Operations; Facilities Engineering Operations; Employee Relations Operations; and Financial Operation.

This document details activities of the irradiation processing department during the month of June 1957. 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.

The November, 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. (MB)

This document details activities of the irradiation processing department during the month of April 1957. 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.

The May, 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.(MB)

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

The liquid high-level radioactive wastes from the separations plant are stored in large underground tanks where radioactive decay of the fission products in storage gives off heat. In the case of the 241-A underground storage tank farm, for Purex wastes, advantage is taken of this heat to self-concentrate the wastes. The present practice is to permit boiling and concentration in the storage tanks. The vapors given off from the boiling wastes are collected in a vapor header and passed through a deentrainment vessel and on to two contact condensers where the vapors are condensed and intermixed with waste cooling water. Samples taken of the waste vapors have shown a considerable amount of cesium{sup 137} present as well as other types of radioactive material carry over from the waste tanks. For this reason the contact condenser effluent is discharged to an underground crib 216-A-8. Underground disposal of the increasing volume of condenser effluent as larger waste volumes are accumulated in the underground tanks presents a critical problem which is further complicated by the desirability to transfer the condensate waste to new disposal facilities near the 200 West area. The intent of this report is to present the scope of the facilities …

E-Metal production is scheduled to start through the UO{sub 3} Plant in July of 1958. E-Metal is defined in HW-46138 as uranium metal enriched with U-235 to a level selected to be always-safe for non-metallic uranium forms, i.e. for compounds encountered during solvent extraction or calcination. Currently E-metal as selected contains 0.94% U-235 prior to irradiation. Planning of a segregation facility requires that the mixing of E-Metal with normal uranium be minimized, thereby preventing costly downgrading. Segregation of E-Metal through existing facilities would require extensive cleanout and flushing. Production scheduling with present demonstrated capacity would make this method impossible. The Redox Plant will produce E-Metal on an intermittent basis. It is expected that normal operating production of E-Metal through the Redox Plant will be quantities of 100 to 200 tons. Production through the UO{sub 3} Plant will follow on this same intermittent basis. During the first two quarters of FY `59 the UO{sub 3} Plant production of E-Metal is forecast at not greater than 100 tons per quarter. Following this initial period the E-Metal production is forecast to run 135 to 200 tons per quarter for the next three to four years. It is the purpose of this document to …

None

Simultaneous reduction of coolant to several or all reactor tubes raises concern not only for the adequacy of protection in the individual process tube but also the reactor as a whole. In event of such flow reduction, the heat generation does not decrease until at least 1.4 seconds have elapsed following the accident. Thus, the water temperature from each tube will rise, and result in an increase in the bulk water temperature. If the increase in bulk water temperature is such that saturation temperature at the top of downcomer is reached, pressurization may occur at that point and exceed the maximum recommended working pressure limit (approximately 1 to 2 psig). The purpose of this report is to present experimental data on a series of tests which were made to simulate flow reductions to a K type process tube by simulated front header pressure decreases.

This report addresses the summary report of the Chemical Engineering Division.

None

None

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 Dumbo space propulsion reactor design concept is described, and the theoretical principles upon which the design is based are developed.

Valves for several purposes are listed and indexed, together with pertinent design and performance information and identifier numbers.

None

To estimate the distribution of temperature in the proposed nuclear reactor, one must determine a coefficient of eddy diffusivity and devise a suitable method of computing the heat transfer. Measurements of diffusion in a model of a blanket element for the proposed reactor indicated a gross eddy diffusion coefficient of about 0.002 (? .0005) ft{sup 2}/sec. Thus, the apparent eddy diffusion for the test conditions is about 200 times the molecular diffusivity of water and about. twice that of the liquid sodium. Even approximate methods of applying this result require an elaborate calculation if the primary characteristics of the flow system are to be taken into account. The dispersion of dye in flowing water provided an indication of the diffusion in the model tests. The presence and arrangement of the rods, the effect on the flow?of the spiral wire spacers, and the existence of a comparatively large area on which a laminar sub-layer develops made it impossible to get simple turbulence criteria like those obtained downstream from a screen. Although the results are consequently somewhat unsystematic, they do establish reliably the approximate magnitude of the coefficient of eddy diffusivity. The data were obtained from both line and sectional traverses, the …

A review is given of the various transverse thermomagnetic and galvanomagnetic effects. The coefficicnts and relations between coefficients are listed for both metals and semiconductors. A quantitative annlysis is given of the error in Hall effcct measurements owing to non-isothermal conditions. (auth)