As a part of the five year budget study requested by HOO-AEC, a study of separations waste storage requirements for this period was made. This study took into consideration the variant estimates of amount of irradiated uranium to be processed, and the goals in the waste reduction research and development program. The conclusions of this study were at variance, to some extent, with prior studies. Interest has been expressed in publication of this study to permit independent assessment of its bases and assumptions.

A large number of ``hot spot`` slug failures characterized by intergranular corrosion of the aluminum can have occurred in the past year. The cause of this type of failure may be vertical displacement of one or more slugs in the slug columns. To determine if such displacement may reasonably be expected and to determine the cause and cure of the displacement a set of experiments have been performed in the 189-D laboratory. This document presents data which has been thus far collected. (1) Slugs which are cocked in a process tube are cause for severe-column bowing. Bowing is most severe when the cocked slug is in the downstream portion of the tube. Stopping flow will not realign bowed slugs. (2) Flow seating a slug column can cause slugs to cock and cocked slugs remain cocked even when backseated and the water flow is stopped. (3) When all slugs have undamaged ends and are well aligned with the tube ribs as well as fully seated against the rear nozzle insert, only minor bowing will occur, even when the upstream end of the slug column is restrained. (4) Anodized pieces behave erratically and in an unexplained manner. (5) Flows as much as …

``An Analysis of Redox Sand Filter Data,`` issued June 18, 1954, discussed increases in sand filter activity during the preceding six months, based upon air samples taken by Regional Radiation Measurement Unit of Radiological Sciences Department and upon vertical gamma radiation traverses (unshielded probe) made by the Redox Plant Radiation Monitoring Unit. ``Estimated Activity in the Redox Sand Filter`` dated July 15, 1954, were accurately defined the distribution of the activity within the sand filter by means of a radiation traverse with a partially shielded probe and by analyzing sand filter sand samples. Analysis of the shielded probe traverse data from the period following the last report through the most current data available reveals that the maximum radiation levels as measured by the shielded probe method were observed in July, 1954, and declined steadily, to an equilibrium, primarily from ruthenium decay.

Reactivity measurements have been made in the Hanford Test Pile, comparing the one-piece I&E slug and the wafer I&E slug with the standard solid slug (1.336 inch uranium diameter). The results of these measurements, made by the Experimental Physics Unit of Pile Engineering, are summarized in this report.

The objectives of this research effort concerned with laminated fuel elements are: (1) elimination or at least a substantial lowering of the rupture rate at present power levels and exposures; (2) pile operation at substantially higher power levels; and (3) long exposures, 3000 MWD/AT or greater and, therefore, a high degree of burnup.

It was recommended that the control rods in the septifoils of the reactor be reoriented in order to improve flux shaping; burnout was not mentioned. This memorandum re-examines the problem of orientation of the control rods considering not only flux shaping but also burnout.

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To test theory, models of the interaction of a conical and cylindrical shell, having three different apex angles in the cone and three different ratios of thickness to cylinder diameter, were subjected to internal hydrostatic pressure and the resulting strains at various points were measured. Careful studies were made of the unavoidable imperfections in the models. The results are in substantiai agreement with the Wenk-Taylor approximate theory described in TMB Report 826 and with the approximate theory of Geckeler. Comparisons are aiso made with other theories. (auth)

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The use of a water boiler reactor as a danger coefficient test instrument has been investigated, with emphasis on the testing of reactor materials for neutron absorbing impurities and the testing of uranium for enrichment variations. After calibration of the WBNS course control rod, tests were made on a variety of materials including beryllium, boron trifluoride, iron and steel, natural uranium metal and oxide, and uranium metal of various enrichments. Several experiments were conducted to evaluate the sources and magnitudes of errors in danger coefficient testing. On the basis of the data obtained from sample testing and auxiliary experiments, the sensitivity of the WBNS for absorption and enrichment testing was determined, as well as other constants relating to danger coefficient measurements. The Water Boiler Neutron Source has been found to be well suited to danger coefficient testing. Small absorption differences between samples of similar geometry and nuclear propenties can be determined to a standard deviation of 0.002 cm/sup 2/. The danger coefflcient technique using the WBNS compares favorably with other methods of absorption detecting methods, such as the shotgun test or chemical analysis. Enrichment differences between natural uranium samples of only 500 grams can be detected to plus or minus …

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