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Analytical methods are given for determining the composition and impurities of beryllium carbide. A summary of the experimental work leading to these procedures and supporting data are also presented. Analytical procedures for the determination of free and combined carbon, moisture, nitrogen, beryllium oxide, silica, iron, total beryllium, and beryllium metal are outlined. Diagrams of special apparatus used are included. (auth)

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This report from the Chemical Processing Department at HAPO, discusses the following: Production operation, purex operation, redox operation, finished products operation, power and general maintenance operation, financial operation, facilities engineering operation, research and engineering operation, and employee relations operation.

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The February, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

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This document details activities of the irradiation processing department during the month of February 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 operations; employee relations operation; and, financial operation.

Production Pu nitrate and unfabricated Pu metal during Feb. was below forecast; however FY output is above forecast. Production of UO{sub 3} exceeded commitments; shipments met schedule. Decontamination performance of Purex solvent extraction system was subnormal. Pu nitrate solutions were concentrated. A fire occurred in Purex N Cell during conversion of ion exchange prototype to production facility.

The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise inside the containment shell. The kinds, amounts, and total radioactivity of fission products released to the atmosphere of the containment shell after the core melts were predicted. (M.C.G.)

The temperature field in an outer rod of the Experimental Gas Cooled Reactor fuel assembly is presented. The numerical analysis has taken account of the three dimenhas considered the four resons involved. that is. fuel pellets, ceramic disc, steel end caps. and cladding. The convective heat transfer coefficient and fluid temperature were considered constant over the 2.185 in. of rod length studied. (auth)

Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.

This report, from the Chemical Processing Department at HAPO for February 1961, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.

The transport of fission products from points of origin in unclad graphite matrix-type fuels to the reactor circulating system involves, as one of the steps. diffusion through the graphite matrix to the fuel element surface. As pointed out by Rosenthal. the fraction of a given fission product chain actaally reaching the fuel element surface will be small if the time for transport through the graphite is long compared to the half-lives of the volatile members. An important problem, therefore, is the determination of the effective transport rates of the various mobile elements and their daughter products of interest through various graphites suitable for use as fuel element compacts. as functions of temperature over the range of greatest immediate interest to reactor designers. The upper end of the range need not exceed about 1000 deg C. The transport of helium and arbon through various graphites has been the subject of considerable study by Watson. Evans, and other,. and a prelimilnary investigation of the high temperature transport of some ordinarily non-volatile elements has been carried out by Saunders. This work is briefly reviewed in relation to the final problem and the areas in which further information is needed most by reactor designers …

The particle size distribution of UO/sub 2/ powders gave good eorrelation with the sintered density of pellets. The method involves gravity sedimentation techniques. The green pressing step of pellet fabrication was found to affect the particle size distribution of the UO/sub 2/ powders. The magnitude of this effect is considered in characterization of the pressed powders. (J.R.D.)

This report, for February 1962 fro 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.

Metallographic techniques are described which were developed for examining coated and uncoated uranium carbid particles, both in the unsupported condition and in graphite matrices. The structural and compositional variations in various batches and within a given batch are presented, and the effects of various heat treatments on the particles and the coatings are described. (D.L.C.)

The variation in rheologlcal behavior and other physical properties of thoria slurries with the calcining temperature of the thoria powder is explained on the basis of the relation between the calcining temperature and the bulk density of the individual thoria particles. Indirect experimental measurements of the bulk particle density by viscosimetry and by measurement of centrifuged- bed denslties agreed wlth each other and fell within the predicted density limlts of 3.7 g/cc and 9.7 g/cc (for oxalateprecipitated thoria). Nitrogen adsorption porosimetry of one sample was consistent with the bulk-density measurement. (auth)

A syntax checker was designed based on the syntax of Algol as previously described. It was desirable to design the syntax checker as a set of mutually recursive processors tied together by building blocks which perform certain bookkeeping functions. Because of the recursive nature of the language and of the syntax checker, the problem of recovery after an error required much attention. A method was devised which permits most programs to be checked completely despite errors. The syntax checker was implemented for the IBM 7090 as a part of the SHARE ALGOL processor, and has operated very satisfactorily. (auth)

This report, for February 1963 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; employee relations; weapons manufacturing operation; and safety and security.

A study of the behavior of Inconel at 1500 deg F under realistic dynamic stress states was performed to critically evaluate present criteria used to solve low-cycle fatigue problems and to demonstrate their applicability for the more complex situations. The relative agreement between the static complex stress- creep-rupture results and the low-cycle fatigue data is demonstrated. From the relationships developed for static complex stress-creep-rupture data, it is demonstrated that the magnitudes of the effects of stress state and frequency on low-cycle fatigue can be determined. (auth)