A capillary-drop method of producing spherical shapes of brittle materials less than 0.l00 inch in diameter was developed. It appears to be a feasible means for producing large numbers of pebble-tyne fuel element cores. Coating of pebble-type fuel element cores by the coating-pan technique, though not adequately developed, showed promise. (auth)

Structures are subjected to a 50-kt blast, in order to obtain fundamental data on structures subjected to blast loading, to observe the response of the structures under this loading, and to determine the relative blast-resistance merits of several structural types. Modes of failure are determined. Shaped structures are found to be superdor to rectangular structures. Earth cover for the structures is also found to increase the blast resistance. It is found that standard Navy heavy bomb-proof structures with modifications can withstand a near-surface atomic burst at ground zero. (T.F.H.)

The Hanford metal wastes were divided into four categories: supernate - the liquid waste; hard sludge - dense agglomerates of poorly defined crystalline carbonates approximating the hardness of soft blackboard chalk; soft sludge - an easily slurried semi-solid consisting chiefly of needle-like phosphates; and recombined sludge - a representative sample of the solid wastes as received from Hanford, shown to be a mixture of hard and soft sludges in the ratio 2/3 by weight. The density of supernate, in the temperature range 24 to 74/sup 0/C, varied from 1.130 to 1.103 g/ml. Hard sludge density averaged 3.0 g/ml and that of soft sludge averaged 1.84 g/ml. The consistency, or apparent viscosity, as a function of temperature, shear rate, and solids content was measured individually on slurries of recombined, soft, and hard sludges using supernate as the suspending medium. Settling rates were also run on these 3 slurries as a function of solids content.

The iodine species formed either by adding hypochlorite to a basic iodide solution or by adding triiodide to sodium hydroxide, was identified as hypoiodite ion. The absorption spectrum of IO{sup -} was investigated in the wavelength range from 450 m{micro} to 280 m{micro}. The kinetics of the reaction I{sup -} + ClO{sup -} = IO{sup -} + Cl{sup -} was studied spectrophotometrically in alkaline solution. The forward rate law was found to be d(IO{sup -})/dt = k(I{sup -})(ClO{sup -})/OH{sup -}. At 25 C and an ionic strength of 1.00 M, k is 61 {+-} 3 sec{sup -1}. It was found spectrophotometrically that for certain ratios of the initial iodide to hydroxide concentrations, there was evidence of the presence of I{sub 3}{sup -}, I{sub 2}OH{sup -}, and I{sub 2}O{sup 2-} along with IO{sup -}. The equilibrium constants between IO{sup -} and these three species were evaluated by a graphical method. The formal potential of the cell: Pt:H{sub 2}:1 M NaOH : 1M NaOH, KI, NaIO : Au was found to be 1.297 v at 25 C. The equilibrium constant, K{sub 2} = (I{sub 3}{sup -})(OH{sup -}){sup 2}/(IO{sup -})(I{sup -}){sup 2}, of the reaction IO{sup -} + 2I{sup -} + H{sub 2}O …

Definite identification has been made of an isotope of the element with atomic number 98 through the irradiation of Cm{sup 242} with about 35-Mev helium ions in the Berkeley Crocker Laboratory 60-inch cyclotron. The isotope which has been identified has an observed half-life of about 45 minutes and is thought to have the mass number 244. The observed mode of decay of 98{sup 244} is through the emission of alpha-particles, with energy of about 7.1 Mev, which agrees with predictions. Other considerations involving the systematics of radioactivity in this region indicate that it should also be unstable toward decay by electron capture. The chemical separation and identification of the new element was accomplished through the use of ion exchange adsorption methods employing the resin Dowex-50. The element 98 isotope appears in the eka-dysprosium position on elution curves containing berkelium and curium as reference points--that is, it precedes berkelium and curium off the column in like manner that dysprosium precedes terbium and gadolinium. The experiments so far have revealed only the tripositive oxidation state of eka-dysprosium character and suggest either that higher oxidation states are not stable in aqueous solutions or that the rates of oxidation are slow. The successful identification …

As titanium, zirconium, and other of the high melting electropositive metals become more important, the problem of using suitable refractory materials for their casting becomes more important. This paper discusses the method of choosing and testing possible container materials. To make the discussion more specific, titanium is used as an example. As titanium melt at 2000 {+-} 10 K, it is immediately clear that one is restricted to refractory materials melting considerably above 2000 K. This greatly limits the possible materials that might be considered. The possibility of using any pure high melting element can be quickly eliminated as titanium reacts quite vigorously with non-metals such as carbon and due to its high boiling point and therefore high internal pressure, one can predict that it dissolves even the most refractory metals. Examination of phase diagrams confirms that even metals such as tantalum, tungsten, and rhenium would not be able to resist attack by titanium. One is thus limited to high melting compounds such as the oxides, sulfides, nitrides, carbides, silicides, and borides. The first consideration is that, if possible, one would use a compound which is thermodynamically stable in the presence of titanium metal at 2000 K. Titanium should not …

At about 6:30 a.m. one of the two Process Operators regularly stationed at 233-S was performing routine work in the Control Room, heard a nearby Poppy alpha detector breaking down.'' He checked and found the instrument appeared to be in operating condition as it would respond to a high level source. Further checking indicated that he was contaminated and that nearby horizontal surfaces were contaminated. This information was phoned to the Shift Supervisor who told the Operator that he would be right out and to throw a pair of shoe covers out the door. On arriving, the Supervisor donned the shoe covers and then quickly checked the Poppy response and confirmed the report of the Operator. Both men then left the building. Just outside they met the other Process Operator assigned to 233-S, returning from the lunchroom. The second Operator was handed a smear, previously taken and checked by the Supervisor, and told to check it on a Poppy in the load-out-room, a room adjacent to where the contamination was originally found. When the Supervisor heard the load-out-room Poppy break down as the smear was checked he instructed both Operators to stand by just outside the building while he went …

During the first 15 months of operation of the Redox process, it was clearly demonstrated that in the absence of any pre-solvent extraction treatment of the starting metal solution, ruthenium contributed from 75 to 95% of the remaining fission product activity in both the final uranium and plutonium streams, and that three solvent extraction cycles were able consistently to produce, at best, only marginal quality product. This precarious position was further endangered by a three-fold reduction in the gamma radioactivity specification for recovered uranium shipped from Hanford, and by increased power levels in the reactors, resulting in still higher fission product concentrations in Redox feed solutions. The purposes of this review are to summarize briefly: (1) the chemistry of Ru in the Redox process; (2) the permanganate head-end treatment and its associated problems in plant operation; and (3) alternate possibilities for the elimination or control of Ru, including those which might solve the permanganate process difficulties. It is also the purpose of this document to present a selected bibliography on the subject of ruthenium specifically for those points under discussion herein. 17 refs.

The following calculations have been made at the request of H.R. Schmidt to determine the probability that self-radiation may play a substantial role in the decomposition of the ruthenium tetroxide in the reflux scrubber, section of the Redox Ruthenium Oxidizer (H-4). The validity of the derived data necessarily depends upon the correctness of the basic assumptions made with regard to process conditions and to possible radiation-activated mechanisms of disintegration. It is estimated that the extent of solid ruthenium formation in the tower which results from radiation effects should not exceed 100 micrograms per batch. This rate is negligible compared to that now found in the presence of stainless steel packing, or to that which might be expected from thermally-activated disintegrations alone.

Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rods were in the ``full in`` position their poisoning effect outside the flattened region at the near side of the pile would be small. By using these ``half rods`` in conjunction with ``short`` rods it was expected that a nearly symmetrical horizontal temperature distribution could be maintained. A comparison of near-to- far temperature distribution at C-pile with other piles indicates that gains in production of 4% during early operation of a pile and 3% during later equilibrium operation can be realized by using the half-rods. On the basis of these observations ``half-rods`` are to be incorporated in the K-piles currently under construction. It is recommended that the ``long`` control rods in existing piles be replaced by rods altered …

Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of the fuel elements within the reactor process tube, worn tube ribs, etc., are believed to cause the high local jacket temperatures necessary for the occurrence of intergranular corrosion.

Pile Engineering Sub-Section has been investigating the causes and effects of cocked slugs in process tubes for the past year because they are suspected to be the cause for some slug ruptures. In Project CG-642 - Continuous Charge-Discharge Equipment - C Reactor it is proposed that slugs be flush charged into the process tubes. This document reports the effect of flush charging slugs on their tendency to cock as discovered in laboratory tests.

Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.

The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it is necessary that a study program be undertaken to determine in general terms the plant changes required to support these forecasted levels, to evaluate the economic and technical feasibility of achieving the process conditions, and to present an integrated program for achieving these objectives. This study program will necessarily consider the interrelated effects of a number of various facets of reactor and water plant process conditions, operational requirements, and proposed development programs. The purpose of this document is to present a plan for the execution of the proposed study. Included in this outline are a review of the basic study considerations, problem assignments and schedules, and manpower and cost estimates for the performance of the …

This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which they are primarily interested.

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This document describes the scope of the C-431-B Reactor Production Facility. In dealing with the broad phases of the project, it includes the Sections ``A`` (Scope Modifications) of the approved Design Criteria, modified to ensure correctness to date. Location of the facility has been set as shown on the site map in HDC-2101, designated site number one. Included in Project C-431-B are the 105-C Building, including within that building facilities previously located in the 1608 Building, a contaminated effluent crib adjacent to 105-C, and gas facilities using the 115-B Building interconnected with 105-C. Also included are an oil shed, a thimble storage cave, a badge house, and an exclusion fence. Building services and process lines will be considered part of the project to a location nominally five feet outside of 105-C.

This document consists of three photographs of ruptured fuel elements. The position, date charged, date failed, exposure, power, lot and failure type are given for tube 3655-KE, tube 4153-KE, and tube 3849-KE. (GHH)

This is a progress report of the production reactors on the Hanford Reservation for the month of May 1951. 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 is a progress report of the production reactors on the Hanford Reservation for the month of May 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.

Eight Zircaloy-2 jacketed, natural uranium seven-rod cluster elements were irradiated in a KER loop to determine flow channel temperature characteristics. One of the elements, which had 200 MWD/T exposure, was sent to the Radiometallurgy Laboratory for examination in April 1959. An outside rod of the cluster was sectioned and examined metallographically. No cracks or flaws were observed in the uranium cladding or bonding.

This memorandum provides a comparison of monthly slug ruptures at the Hanford C-Pile.

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

This document presents a summary of work and progress at the Hanford Engineer Works for May 1953. 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 summaries 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.