None

A desirable radio-iodine emission goal for all HAPO has recently been set at one curie per day maximum. At the same time it was suggested that a more relaxed limit of ten curries per week with no more than three in any one day, would probably be satisfactory. To assure the achievement of these goal figures in the separations plants it was deemed necessary to either cool'' the irradiated material a greater length of time than is presently done before processing, or provide more efficient, iodine retention facilities. Increased power levels, higher production rates, and an increase in the awareness of radio-iodine emissions, have all coupled together to make present facilities generally inadequate when processing material aged less than about 100 days. Several alternate methods of providing additional iodine retention facilities for Redox were preliminarily scoped and presented for consideration. The purpose of this report is to present a scope design for improving iodine emission control at Redox.

This document discusses a production test which was written when the piles were operating under a graphite temperature limit of 410 C. Operation was controlled by as-read temperatures of the originally installed G thermocouples, by thermocouples installed on vertical safety rod thimbles, and by thermocouples in graphite cylinders installed in the C test holes. Since the thimble thermocouples were to be removed under the Ball 3X program, it was planned to install thermocouples in some of the process tube channels to help monitor the graphite temperatures. In order to ensure maximum production levels based on graphite temperatures, the proper temperature relationships between the channel thermocouples and the G and/or C test hole thermocouples were needed. The expected maximum allowable channel thermocouple temperature reading would be higher than the burnout temperature limit of the graphite in the-pile.

The intent of this study is to establish more completely the justifications for constructing a decontamination plant as outlined in Budget Item B 5720, ``Containmented Equipment Renovation Shop,`` FY 1957, Plant and Equipment Projects. In particular, the economic incentives have been explored. The question or idea has been investigated of assigning a dollar value to engineering information which might be obtained from examining contaminated equipment which has failed from unknown causes. Heretofore it has not been possible to examine such equipment because suitable decontamination facilities have not been available. An effort has been made to uncover all possible uses for the proposed facility in order that the estimated capital and operating costs might be evaluated in terms of all the functions which the proposed plant might perform.

This document presents a summary of work and progress at the Hanford Engineer Works for July 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and services departments have sections presenting their monthly statistics, work, progress, and summaries.

The operation of a Priest Rapids dam is stated to necessitate river flow manipulation varying from 25,000 cfs to 120,000 cfs in the winter months of a critical water year. The low flow may persist for periods of six hours daily, and the expected daily average low flow is 61,000 cfs. The possible effects of this on reactor operation and waste disposal to the Columbia River which are of the interest to the Radiological Sciences Department were reviewed by J.F. Honstead, R.E. Rostenbach, and R.F. Foster. These include radiation hazards in reactor area water treatment plants, reactor area drinking water contamination; increased river temperature; chromium pollution problems; effects on downstream river usage, and effects on aquatic life.

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.

The isotope Na{sup 24} is one of the major short half-life constituents of reactor effluent water. It has a half-life of 15 hours and decays of emission of a 1.39 MeV maximum beta particle. Other radioisotopes present in reactor effluent water from which Na{sup 24} must be separated are Si{sup 31}, P{sup 32}, Mn{sup 56}, Cu{sup 64}, As{sup 76}, Sr{sup 91--92}, Ba{sup 139--140} and rare earths. This report describes a rapid and very simple method for the quantitative determination of Na{sup 24} in a radiochemically pure form.

A discussion is presented of the elements, or at least most of the elements, that are usually thought of as required and characteristic of living materials. A continuous evolutionary process is conceived, beginning with a bare earth and leading to the random formation of more or less complex molecules from simple ones, and gradually, by the processes of random variation, autocatalysis, and selection, to more complex systems and the ordered array of desoxynucleic acid molecules which are the units that carry the continuity and order of present-day living systems.

None

None

None

None

None

None

8 5 6 2 0 5 8 5 5 ? 5 : tion of the HRT is summarized. The design of some reactor components is described, including fuel system line coolers, the thermal shield, instrument cubicles, the reactor cell air monitor, and sampling facilities. The important design specifications for the HRT fissionproduct adsorption system are outlined. The effects of fluid circulation on HRT stability, the results of the rupture of the fuel inlet nozzle on the pressure vessel, core tank temperature, and heat generation and temperature distribution in the control room area shield were examined. Operation of the HRT mockup loop is summarized. High generalized corrosion rates and U precipitation were observed when 50 ppm oxygen was used. Results from tests of HRT pumps, heat exchanger, sampler mockup, and reflex condenser and recombiner are presented. Design of the instrumentation in the control room area and fabrication of differential pressure and liquid level transmitters are reported. Thorium Breeder Reactor. Stability criteria, the effect of slurry settling on reactivity, and neutron losses due to coating the core tank with platinum bave been analyzed for the TBR. An economic study of partial fuel costs for one-region Pu-U reactors was completed. The design concept …

None

None

Evidence is presented which indicates that chelating ability may be greatly altered by changing the steric requirements of the ligand. A series of formation constants was measured for three beta-diketones. Thermodynamic values could not be obtained but relative concentration constants were. The constants obtained were correlated with each other and with the basicity of the reagent toward a proton. Each correlation indicated that the formation constants for the copper chelates of diisobutyrylmethane and dipivaloytmethane were low and exhibited large separation factors. However, relatively small separation factors were found for metal chelates which do not form square planar complexes. A simple method for determining the extent of enolization of beta-diketones and the kinetics of enolization is presented. The method makes uses of spectrophotometric measurements in the ultraviolet region. Correlations were observed between the pKa of the chelating agent, the kinetics of enolization, and the kinetics of hydrolysis of corresponding esters. Variations in the pKa and enol content were explained on the basis of steric effccts. A procedure for the separaticn of lithium from other alkali metal ions was developed, making use of the selectivity of dipivaloylmethane. The theoretical implications of this selectivity are discussed. Correlation of formation constants with a double …

None

Three independent measurements of the work function of uranium have been reported. The values obtained were were made with uranium wire and since, as shown by the authors, uranium is very readily oxidized at pressures of 10/sup -7/ mm Hg to give a relatively non-volatile oxide, one surmises that some of these determinations were subject to error because of vacuum conditions. Attempting to investigate the validity of this criticism, the authors have measured the thermionic properties of a uranium wire in such a manner that some information regarding the cleanliness of the surface can be deduced. The two types of measuremente accomplished were the change in the thermionic constants of the Richardson equation with time of heating in hydrogen, and the dependence of current on the retarding potential. (auth)

None

None

None