``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.

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.

Tables are presented for free energy and heat of formation for salts (oxides, sulfides, halides) metals often encountered in metallurgy.

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BS>It is assumed that when a hole appears in the cladding of a reactor fuel tube the fission products in the space between the fuel and the cladding will diffuse towards the hole. There they are swept away by the flow of steam past the hole. The process of diffusion is assumed to be governed by the ordinary diffusion equation with the boundary condition that the density of the fission products is zero at the surface of the hole. The diffusion equation is solved for the case of steady-state emission for a number of geometrical arrangements: long slit in plane surface; long slit in cylindrical surfaces circular hole in plane surface; circular hole in cylindrical surface; hole at end of cylindrical fuel rods and diffusion space of variable thickness. The timedependent solution of the diffusion equation is also found for a planar diffusion space. The effect of a temperature gradient is discussed. (A.C.)

A comparison of B and Hf for use in APPR control rods shows that it is possible to substitute Hf plate. Increased wall thickness of Hf will result in a smaller water volume, but reduction of the moderating center will not decrease the effectiveness of Hf rods. Burnup of Hf results in only small change of the initial blackness. Since neutron absorption in most of the Hf isotopes are (n, gamma ) reactions there is no heat generation in Hf rod. (W.L.H.)

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This paper discusses the estimated effects of silver salts from regeneration of iodine reactors on waste cribbing at Redox. (KJD)

The reference letter dated October 4, 1956, requested that they review the possibilities of a crippling accident in 232-H and the measures which might be taken to minimize the loss in tritium production associated with such an accident be reviewed. These subjects have been reviewed in considerable detail and the authors feel that the chances of a crippling accident are quite remote. In arriving at this conclusion, the entire process was reviewed and the following three incidents were selected as having the most serious potential. (1) a tank containing tritium at subatmospheric pressure develops a leak and becomes contaminated with air equalized to atmospheric pressure; (2) a flange is removed inadvertently or a nozzle breaks on a tank containing tritium at 15 psig; (3) the water jacket on the extraction furnace ruptures internally, particularly when the charge is molten. From the foregoing, it may be concluded that a serious accident in one line is unlikely to shut down the other from the standpoint of either physical damage or serious contamination. It should be recognized that some outage, perhaps a matter of days or even weeks, could result while safety of operation is assured. Insofar as procurement of long delivery equipment …

It has been proposed that facilities be provided which can be used to divert the Purex cooling water from the facilities already proposed on this project to a depression within the 540 ft. elevation contour at approximate plant coordinates 34,300 N, 40200 W. These facilities are in addition to the change of scope referred to in reference (1). The purpose of these new facilities is to forma hydrologic dam as part of the ground water table which would aid in the confining of contamination and/or restricting the movement of contamination in the south easterly direction.

This report presents information on the design and operation of the condensate disposal system for your use in design studies to rectify present limitations of the Purex 241-A Waste Tank Farm condensate disposal facility.

This report contains tabulations of the approved waste limits for Hanford plants. These data are to be used in making allowable waste calculations.