This report presents results on radiation monitoring from the radiological sciences department for January, 1955. Information is presented concerning radioactive effluent releases, personnel skin contamination, air sampling, and general radiation monitoring from the facilities.

A survey was made on methcds and related costs of disposing of radioactive wastes as practiced in 1955 by twelve atomic industry installations. Wherever possible, estimated unit costs of differentiated stages of waste handling are shown- these are integrated to show the over-all scope of waste dispesal practices at each site. Tabular data summarize costs and operation magnitades at the installations. A pattern is established for standardizing the reporting of fixed costs and equipment unsage costs. The economy of solid waste volume reduction is analyzed. Material costs are listed. An outline for recording monthly waste disposal costs is presented. Obvious conclusions drawn from the factual data are: that it is more expensive per cubic foot to handle high-level wastes than low-level wastes. and that land disposal is less expenaive than sea disposal. A reexamination of baling economics shows that high compression of solid wastes is more expensive than simpler forms of compaction. (auth)

The literature, for the period 1935 through 1954, was reviewed for information pertaining to the determination of the alkali metal and alkaline-earth elements by photometric methods. Those references, in which studies were presented of the interference of one or more of these elements on the flame photometry of another cation of the alkali metal or alkaline earth groups, were of particular interest.

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The status of Experimenial Boiling Water Reactor development is reviewed. Shell testing, control mechanism development, fuel corrosion, and dimensional stability studies, and design consideration to facilitate D/sub 2/O operation are discussed. Fuel plate and subassembly fabrication, corrosion, and radiation damage studies were continued. Reactor water filtration, purification, and induced activity are considered. High-temperaiure operational tests were run on Experimental Breeder Reactor mechanisms. Though several minor malfunctions were encountered, the basic operation is considered satisfactory. Studies of the physical and metallurgical properties of U -- Mo, U - Zr, U -- Pu, and U -- Pa -- Mo alloys for fuel elements were conducted. Conversion ratio deiermination for the second loading of EBR-I gave a value of 1.03 plus or minus 0.05. Alloys and systems w-ere irradiated anci the effects of the irradiation on corrosion determined. Included in the irradiation were U, U - Si, Nb - Sn, UO/sub 2/, and Al - Ni. (For preceding period see ANL-5476.) (D.E.B.)

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A study was made of fiber-texture type of preferred orientation in extruded Al rods and brass sheeting. Experiments to purify Zr by the zone- melting techniques were studied. Several transformation products of the decomposition of the BETA eutectoid of the Ag--Zr system were identified. The tempering of the martensitic structure of a hypoeutectoid Ag-- Zr was studied. Metallurgical treatments for the recovery of U from spent stainless steel fuel elements were investigated. Physical properties and radiation stability of the Si-- SiC fuel element material were investigated. The development and fabrication of a uniform fuel-bearing sandwich plate were continued. Methods of welding stainless steel were studied. An evaluation study was made of brazing alloys on the basis of corrosion resistance, neutron economy, flow temperature, availability, and cost. (C.H.)

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This document was prepared in response to a request from the Atomic Energy Commission for a brief review of the principal ideas and technical developments which might effect power levels over the following six years. Also requested were approximate data on any pile modifications that might be involved, including rough estimates covering possible cost and completion dates. A brief discussion of plans for increasing the power levels of the Hanford Piles is provided.

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During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operationally feasible. It is anticipated that in the future other tube outlet water temperature limits will be developed based on new technology. The purpose of this document is to present, in simple terms, an understandable explanation of previous operating limits, to discuss the status of the present Instability Limits, and to outline the direction of future work in raising the outlet water temperature limits.

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The design and construction program of the Bolling Experimental Reactor is reviewed. A number of preliminary experinnents were performed with Borax-II at pressures between 75 and 300 psi. The most corrosion-resistant U-Zr--Nb alloy developed so far is produced by heating in a vacuum to the gamma phase, quenching, and aging for 2 hr at 400 deg C. Special attention is given to the removal of H/sub 2/ from the material. Unclad and unirradiated samples of U--Nb and U--Nb--Zr alloys were corrosion tested in H/sub 2/O. Corrosion rates were also measured under irradiation conditions in CP-5. Elongation measurements of irradiated wrought and cast U--Zr material suggested no way for treating the wrought fuel so that stability comparable to the cast material could be obtained. Natural circulation boiling density tests at 600 psia were made in order to determine the effects of channel cross section and subcooling on the steam void fraction. Results of autoclave and dynamic corrosion studies of 2-S Al in H/sub 2/O are reported. These results include the testing of Ni-clad samples. A large number of criticality calculations were performed for the EBR-Il and the PBR. The solubility of ThO/sub 2/ pellets containing various concentrations of U/sub 3/ O/sub …

This report discusses two methods which have been considered to reduce the rear face activity. The first involves the use of a solids purge to scour out the activity, and the second employs the use of a chromic acid purge to put the activity into solution. Solids purging is found to be ineffective in reducing rear face activity levels. A chromic acid purge conducted at 60 C for 1/2 hour can be expected to reduce the Zn{sup 65} activity level about five fold without injuring the reactor or causing any harmful aftereffects.