Current Panellit protection procedures, termed instability limits, come from calculations based on steady state experiments. However, the actual conditions in a process tube following a plugging occurrence sufficient to cause unstable flow are transient rather than steady state, and cannot be determined with great precision except by transient state experimentation. As a result, a program was initiated by the thermal Hydraulics Operation of HLO to perform a series of transient heat transfer experiments which would define the process tube response to (1) rapid plugging in the process tube assembly, (2) slow plugging in the process tube assembly, and (3) power excursions above normal of varying amounts. Transient heat transfer experimentation on a large scale is not common and many difficulties have been encountered. After preliminary runs were made and reported, a further series of runs were planned and run which would include K as well as BDF type data and would define more closely the upper limit of the panellit protection. During the test runs, data from these transient experiments are recorded on high speed recording instruments, each of which has a calibration which is subject to change regardless of the efforts expended by the experimenters. This means that checking …

This report addresses the constitution of zirconium-uranium alloys containing oxygen or nitrogen.

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A wide range of irradiation testing facilities and services are present at the Hanford Atomic Products Operation. A number of these facilities are described as a means of illustrating the testing equipment and techniques which are currently in use. (auth)

The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed. (auth)

A preliminary analysis has been made to compare the performance.of a ceramic ramjet reactor powerplant, such as described in General Electric Report No. XDC-56-5-81, with that of such a powerplant supercharged by a metallic-vapor-cycle compressor jet. Performance at sea level, Mach 2.5 is ·reported for the vapor-cycle compressor jet alone, for the ramjet alone, and for the compressor jet - ramjet combination. Results indicate that adding the compressor-jet as a supercharger for the ramjet provides an increase in specific thrust of about 20 percent over that of the ramjet alone, with an attendant increase in thermal efficiency of about 20 percent over that of the ramjet alone.

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The rates of growth of diffusion layers between U and Al and between U and AlSi alloy (eutectic composition) were studied and compared over the temperature range 250 to 55O deg C. Metallographic observation shows that the U-- Al reaction layers form three to five times as fast as the U-- AlSi layers over this temperature range. Sixty per cent of the layer growth takes place in the Al or AlSi alloy and 40% in U. (auth)

Results are presented from film dosimeters and gold and suifur threshold detectors used to measure gamma radiation neutron fluxes. The bulk of the data reports the results of naeasurements in various shelters and homes. The data are presented in tabular form by project number and shot name in Appendix A. The report also contains results of studies on the effects of neutrons on film dosimeters. (auth)

State, Government, and ASME Codes are given for the radistion exposure, waste disposal, piping, and pressure vessels for the PWR reactor plant. (W.L.H.)

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The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

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