Chlorine may be determined in polyurethane by gravimetric or spectrophotometric techniques. The sample is burned in a special combustion tube with two oxygen inlets, the products of combustion are absorbed in a solution containing sodium hydroxide and hydrogen peroxide, and the chlorine is measured either gravimetrically as silver chloride or spectrophotometrically using mercuric thiocyanate and ferric perchlorate. Eighteen determinations of cblorine in known solutions of sodium chloroacetate or perchloric acid gave an average recovery of 98.3% with a standard deviation of 2.8%. (auth)

Progress is reported on the following investigations: pilot-plant evaluation of U ore concentrates; low-acid extraction of U; scrub-column operation, corrosion of reactor materials in sparge tanks containing UNH; effect of UO/sub 2/F/sub 2/ content on UF/sub 4/ reduction; thermal densification of UF/ sub 4/,; operation of the moving bed reactor; reduction of UF/sub 4/ with Mg; development of a mold insulator; preparation of Th (C/sub 2/O/sub 4/)/sub 2/ and ThCI/sub 4/; production of Th metal; ore resistant t transform ation of U; effect of H/sub 2/ content of slug canning behavior; centrifugal casting of slugs; determination of Zr and Mo in U alloys; and analysis of U and Th ores for rare earths. (W.L.H.)

The KEWB Program is devoted to the study of the dynamic behavior of homogeneous type research reactors. The objectives of this program include studies to develop better and more complete understanding of phenomena which contribute to the kinetic behavior and the inherent safety of the water boiler reactor. The approach to the objectives has heen to construct a prototype 50 kw homogeneous reactor with the necessary auxiliary apparatus and to study the transient behavior of the system as a function of the more significant parameters which affect this behavior. These include the amount of reactivity release, rate of reactivity release, initial core pressure, initial core temperature, initial reactor power, and void volume above the core. Data are plotted. (auth)

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements V through Sn at 0.001 to 14.5 Mev. (C.J.G.)

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements hydrogen through titanium at 0.001 to 14.5 Mev. (C.J.G.)

Submitted as a thesis by William Berdell Barlage, Jr. Heat transfer studies were refined and extended to the point where the results could be generalized into a mathematical correlation valid over a reasonably wide range of variables. An extended study was made of the rate of heat transfer between benzene and water in direct contact in a pulse column, and of the operating variables which controlled the behavior. In this mode of heat transfer the benzene was dispersed as a family of droplets into the water, which formed the continuous phase. The pulse column was 1.92-in. in inside diam., and contained 8 stainless steel perforated plates spaced 2.00 inches apart. The plates were perforated with 1/8-in. holes in a triangular 60 deg pattern, providing 24.6 per cent free area. The equipment was carefully insulated and modified in many details in order to permit precise heat transfer measurements. The operating conditions were varied so as to provide wide ranges of variables and heat transfer responses. (W.L.H.)

References to signiflcant design information for a steam generator in a gas-cooled reactor system are presented. Papers concerning heat transfer and pressure drop correlations for gas flow across banks of bare and circular finned tubes and for subcooled waters boiling water, and superheated steam flow inside pipes are listed and briefly discussed. (auth)

The unclassified literature covering 2498 reports from 1907 through 1957 has been searched for isotopic exchange and isotepic separation reactions involving U and the lighter elements of the periodic chart through atomic number 30. From 1953 to 1957, all elements were included Numerous references to isotope properties, isotopic ratios, and kinetic isotope effects were included. This is a complete revision of TID-3036 (Revised) issued June 4, 1954. An author index is included. (auth)

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A general survey is presented of information in the uranium alloy field. Emphasis is centered on alpha uranium-rich alloys of special interest as uranium- base fuel element materials. The systems treated include uranium-molybdenum, uranium-silicon, uraniumzirconium, uranium-niobium, and uranium-zirconiumniobium (high uranium compositions). The uraniumfissium alloys are discussed in relation to their projected applications as fast reactor fuels. Equilibrium diagrams, transformation kinetics, and other pertinent data are presented for the uranium plus fissium'' element systems, e.g., uranium-ruthenium, uranium-rhodium, uraninum-palladium, and uraniummolybdenum-ruthenium. The properties covered include constitution phase diagrams, metallographic structure, physical and mechanicaly properties, transformation kinetics, crystallographic structure, thermal cycling, ad irradiation stability (where pertinent). Correlations between microstructure, heat treatment, and dimensional stability are emphasized, with particular reference to the U-2 wt.% Zr, U-5 wt.% Zr, and 1 1/2 wt.% Nb alloys. A discussion of the role of alloying and heattreatment in improving the dimensionaly stability and corrosion resistance of uraaium is presented, and an evaluation is made of the present status in attaining these objectives. (auth)

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Thirty-seven sterile materials of common construction usage, common lubricants, and samples of wearing apparel were injected as finely divided particles into the subcutaneous soft tissues of guinea pigs, each in six different sites. At intervals of 3, 7, 14, 21, 30, 65, or 90 days, an inoculation site of each material was excised, in toto, fixed, and examined microscopically. In addition, ten selected materials were injected into the liver and spleen and deposited on the omentum and mesentery of four guinea pigs for each material type. At intervals of 7, 14, 21, and 30 days, one of each group of four animals was sacrificed and a block of tissue containing the inoculum was removed from the tissues and organs, fixed, and examined histologically. The majority of materials induced only a mild and delayed inflammatory response followed by encapsulation at the end of 14 days and a relatively inert fibrous nodule produced by the 2lst or 30th day. Copper particles incited a marked inflammatory response with abscess formation which persisted until the 90th day, although showing signs of subsiding at this time. Cudmium lesions were characterized by a peculiar zone of necrosis about the particle aggregate which persisted until the 60th …

The experimental program performed in the SRE auxiliary and main primary galleries was part of a program to determine the adequacy of the shielding configuration for the SRE. The work discussed in this report is concerned with analysis of neutron streaming at coolant pipe penetrations of the reactor vessel, analysis of the shielding required, testing and evaluation of recommended shielding, and measurement and correlation of neutron streaming in labyrinths with theory. The activation analysis method using zinc sheets which was developed for the program of determining thermal neutron streaming in the SRE primary galleries was proven to be versatile, accurate, and reliable. A modified form of the theoretical method of Price, Horton, and Spinney, used to determine neutron scattring through labyrinths, was found to agree favorably with the experimental results obtained from the SRE primary galleries. The theoretical attenuation method used no determine the neutron shield configuration installed in the auxiliary primary gallery was found to give an overestimate of the actual attenuation properties of this shield. The neutron shield configuration installed in the auxiliary primary gallery proved to be adequate in reducing the thermal neutron streaming flux to an acceptable level. It is concluded that both SRE primary galleries …

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for September 1956.

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Papers are presented in the following major categories: applied metallurgical research, natural-uranium metallic fuel elements, enriched-uranium metallic fuel elements, nonmetallic fuel elements, corrosion of U alloys, irradiation effects on U, its alloys, and its compounds, and Pu fuel elements. (M.H.R.)

This is a progress report of the production reactors on the Hanford Reservation for the month of September 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This document presents a summary of work and progress at the Hanford Engineer Works for September 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.