From abstract: "This report discusses a special handling procedure devised to prevent contamination of high-purity gold while processing the metal from cast billet to final sheet. Gold of 99.99% purity was cast into rectangular billets and rolled into sheet whose final dimensions were 48 by 12-1/2 by 0.015 inch...As a final step, the sheet was annealed dead-soft in preparation for subsequent forming operations."

This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.

This document is Revision No. 2 of the ``Process Specifications for Critical Mass Control -- Purex Plant``. It encompasses the changes in flowsheet, equipment and plant operating philosophy that have developed since the plant startup. It supersedes Document HW-44064 (Revision No. 1). Plutonium-239 and uranium-235, either as the metals or as dissolved or solid compounds are capable of spontaneous and violent nuclear reactions. Following initial dissolution of irradiated natural uranium fuel elements the Purex Plant is normally involved in the processing of liquid solutions containing these isotopes. However, in Purex Plant solutions, uranium-235 is invariably associated with a large fraction of neutron-absorbing uranium-238, a condition which precludes the possibility of a nuclear reaction. (These specifications are based on the premise that no enriched uranium is processed in the Purex Plant.) Plutonium-239, on the other hand, is separated from uranium by means of the Purex process; and even prior (process-wise) to its separation, the ratio of plutonium to uranium must be controlled during the off-standard conditions of plutonium rework or recycle. Critical mass control in the Purex Plant is concerned solely with prevention of nuclear reactions of plutonim-239, which has been produced by irradiation of natural uranium fuel elements.

The purpose of this report is to present results of an experimental program directed toward determining the degree of protection offered by the Panellit protection system to flow losses to a single process tube containing I & E fuel elements in K reactor.

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.

From introduction: "This report presents the results of the preliminary studies of two fabrication methods aimed at producing high density beryllia shapes more economically. The method were cold compaction and sintering, and extrusion and sintering."

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The following report records the use of the double-precision THEMIS code to integrate the motion of Mars and Venus in order to obtain a complete set of rectangular equatorial coordinates over the interval 1600-2000 A.D.

The following document is a bibliography containing a collection of documents discussing natural steam and geothermal power generation.

This document details activities of the irradiation processing department during the month of June 1958. 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.

Assistance has been requested by Financial Operation to determine the percent of firm and interruptible power used in each area for cost distribution purposes. Also, Power Operations have suggested that the power cost distribution be reviewed. In consideration of these requests, and with the use of improved demand instrumentation within the 151-B, D, and F substations, a proposal for equitable IPD electrical power cost distribution between areas is presented for acceptance or comment by Area Management.

This document consists of water shutoff data for the K-pile. Included are apparent graphite diffusivity, apparent gas gap at the surrounding tubes, graphite bore radius, apparent gas gap at the test tube, maximum graphite temperature, water shutoff time, overall resistance slug to graphite, and resistance of bore gas annulus to heat transfer.

This is the monthly report for the Hanford Laboratories Operation, June, 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics, instrumentation research, employee relations, operations research, synthesis operation, programming, radiation protection, and laboratory auxiliaries operation are discussed.

The objective of this test is to authorize large-scale irradiations of X-8001 (formerly designated M-388) alloy jacketed fuel elements in order to evaluate their suitability to the reactor process.

2-Carboxy-4-ketopentitol is converted enzymatically by a cell-free preparation from spinach leaves into a substance undergoing acid-lactone interconversion. This substance has no phosphate or letone group and is probably a dicarboxylic, six-carbon sugar acid or the saccharic or saccharinic acid type. The significance of these findings with regard to the metabolic role of 2-carboxy-4-ketopentitol diphosphate is discussed.

The discovery of the delayed light emission of plant materials by Strahler and Arnold in 1951 has stimulated a good deal of interest in this rather remarkable property. The emitted light has been shown to be due to an electronic transition between the first excited singlet state of chlorophyll and the ground state. At room temperature, a luminescence is observable from about 0.01 seconds to several minutes after excitation. Thus, the electronic transition cannot be rate-determining and the process represents neither normal fluorescence nor normal phosphorescence. Indeed, there is some evidence that the decay curve of the luminescence is the resultant of more than one rate-limiting process. Strahler and co-workers have been able to demonstrate the existence of many relationships between delayed light emission and photosynthesis and thus have been led to interpret the luminescence phenomena as a consequence of the reversibility of some of the enzymatic photosynthetic reactions. Moreover, Tollin and Calvin have shown that the faster decaying components of the delayed light are present to as low a temperature as -100 C, suggesting that the early processes following light-absorption are non-enzymatic in nature. These latter observations, in conjunction with several other types of experimental and theoretical information, have …

Two eddy-current electromagnets to act as brskes were designed and installed in the sodium-cooled nuclear pcwer reactor SRE to throttle sodium flow throughout the reactor after shutdown in order to maintain a constant reactor temperature gradient. One brake was used on the primary piping system, the other on the secondary system. It was determined that the eddy-current brake should cause a dragging pressure of 0.3 psi at a flow rate of 12 gal/min. The flux density necessary to produce this pressure was calculated, and the coil ampere- turns required to produce this fiux density were determined. Both brakes were controlled by thermocouples and performance was satisfactory. (M.C.G.)

The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.

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The kinetics of the gamma deg C was con- beta deg C was con- alpha , beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were determined with a fiuid displacement technique. The rates of formation of the alpha and beta phases from the gamma phase were determined after gamma heat treating and allowing a sample to traasform isothermally in the alpha and beta ramges. Isothermal reaction curves were obtained from 160 C to -78C. The time-temperature-transformation curve of the gamma deg C was con- beta deg C was con- alpha transformation was plotted. The effect of the gamma heat treating time and temperature on the rate of transformation was examined. Isothermal reaction curves and time-temperature- transformation curves of the beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were plotted. Photomicrographs of specimens having transformed from the gamma range at different rates of transformation are presented. (auth)

A summary of the Cr data from the HRP in-pile corrosion program is examined in an effort to determine the Cr species present in such solutions under in-pile conddtions. Data from previous in-pile bomb and loop experiments pertinent to Cr behavior are tabulated, and correlations are offered to support a proposed model. It is pointed out that other interpretations of the same data are possible, and to obtain conclusive evidence as to the identity of Cr species in these solutions, especially designed experiments are necessary. (J.R.D.)

Equations are derived which relate the distribution of corrosion attack or cold-zone deposits with the ratecontrolling step of a system which exhibits a thermalgradient mass transfer. Characteristic distributions of attack and deposition are illustrated for thermalgradient mass-transfer processes which are: (1) hotzone controlled, (2) cold-zone controlled, and (3) both hot-zone and cold- zone controlled and the limitations of the method are discussed. It is concluded that both the hot-zone and cold-zone processes must be understood before the conditions leading to the least undesirable distribution of attack can be specified. (auth)

"The purpose of this report is to consolidate data gathered by the Corps of Engineers in various geologic investigations, and to augment this material with pertinent information garnered from the extensive investigations and studies [of the Mississippi River deltaic plain and its associated offshore area]" (p. 1). The report focuses primarily on those materials that are most important from an engineering standpoint.

Adwanced Water Reactor Progran. Seven reaction couples were studied for 60 days at 600 and 800-C:. graphite; lead with Zircaloy-2 amd stainless steel; amd graphite with Zircaloy-2. No reactions were observed at 600 C and only lead-Zircaloy-2 appeared to react at 8OO C. Fast Power Breeder Reactor Program. EBR-I Mark III core is being fabricated. Tests in Borax-rV on sheetu showed fracturing dependent on UO/sub 2/ content. Non-destructive testing development continued. Alloying with Ru showed no improvement in corrosion properties of U. Corrosion of M388 A1 alloy as affected by Vhosphate, pH, and flow rate were studied. Production, Trcatment, amd Properties of Materials. Plastic deformation and thermal conductivity of U single crystals was studied. Ihvestigation of recrystallization of alphaU without a texture change continued. Tests of French uranium are reported. Barrier layers of UO/sub 2/ were found in sputtering of Zr and U onto U, probably resulting from impurities in the argon used. Phase traasformations in the U-C system were studied, and gamma U lattice parameters for 900k C annealed amd water quenched U-Mo-Ru are given. Studies are also reported on the Zr corrosion mechanism and sintering of ceramic materials. (For preceding period see ANL5717.) (T.R.H.)