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From the standpoint of erosion, a long dump line may be preferable to a throttling dump valve to achieve the pressure drop from the HRE-3 slurry blanket to the dump tank. Extended length HRE-3 dump lines in which the maximum average velocity is 20 fps, the smallest allowable line size is 1/2 in., and the time for dumping is 10 minutes are investigated. Twenty-six parallel 1/2-in. Sch. 80 pipes, each 725 ft long, or four parallel 1 1/2-in. Sch. 80 pipes each 2,000 ft long are required. To avoid localized velocities considerably higher than 20 fps as a result ef flashing, these pipes can be submerged in a 25,000 gal pool of water initially at 135 deg F and with 40 deg F allowable temperature rise. It can be concluded that if the velocity, line size, and dumping time are limited to the values listed above, use of restrictor piping to achieve the pressure drop is not very practical. If higher velocities and flashing are allowed, a cursory study indicates that for an average velocity in the range from 100 to 200 fps, one 1 1/4-in. (or smaller) line of less than 250-ft length could be used. Flashing would occur, …

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Calculations are presented of the amount of mass transfer to be expected in liquid alkali metal-Ni alloy systems for two assumed diffusion mechanisms. In one, the boundary layer is assumed saturated and the transfer rate is limited by the rate of diffusion of solute into the liquid. In the other, the mass transfer rate is assumed to be limited by the diffusion rate of a component of the solid alloy to the solid surface. It is concluded tbat a more general hypothesis is needed. (T.R.H.)

The tabulation of pipe lengths, with calculated surface areas and volumes, was assembled from physical measurements of the process piping, included also is a list of instrument lines, with their measured lengths and estimated volumes. (auth)

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)

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The results of a study to determine reliable heat transfer data for the design of a suitable heat exchanger for the Intermediate Scale Homogeneous Reactor are presented. Design studies of a vertical submerged-tube evaporator with nucleate boiling from the outer tube surfaces and of a vertical tube, forced-circulation evaporator are presented in detail. (M.P.G.)

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The electical analog study of the diaphragm feed pump system resulted in changes to the system which have improved the over-all operation and reliability of the pumps. Specifically, the study showed that if the release of the high- pressure oil from the pulsator through the valve on the Scott and Williams pump could be made to take place over a longer period of time, pressure oscillations could be substantially reduced. Also, pressure surges could be reduced by placing an accumulator in the pump discharge line near the check valve. Both of these have been incorporated into sulted in a quieter and smoother operation of the pumping system. (auth)

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The design features and the performance of UO/sub 2/SO/sub 4/ blanket processing Loop P-1 are evaluated from an engineering viewpoint. This unique experiment development loop was operated with pump heating to study the behavior of plutonium in 1.4 M UO/sub 2/SO/sub 4/at 250 deg C and was designed for mixed O/ sub 2/-H/sub 2/ gas pressurization The canned loop and the feed and sampling systems in glove boxes completely contained the plutonium throughout the experimental program. (auth)

Thorium Research. The effect of quenching temperature on the hardness of Th--C alloys is described. The effect of quenching temperature and oxygen content on the hardness of Th--O, alloys is discussed. The effects of Be, Cr, and C additions on the properties of pure Th are described. The mechanical properties, recrystallization, and fabrication of Th are given. Preferred Orientation of Uranium. Fabricating conditions, preferred orientation, and examination of alpha-extruded U rods are given. The creep rate of beta-treated normal U and of extruded Th is given. Properties of some high-temperature brazing alloys are given. Welding conditions are given for cone-arc welding of stainless steel tube-to-header joints. Homogeneous Reactor Program. Analysis of various compacts containing B/sub 4/C are given. Preliminary work on the variables involved in welding Ti was started. Experimental work to determine the effects of various impurity elements on the impact properties of Ti and Zr was started. A metallographic examination of Ames Th cold worked and annealed for 60 minutes is presented. Experimental Plate-Cladding Program. The cladding of Th and U with Zr is discussed at length. The cladding of Th with Al is described. Experiments on welding of Th, U, and Zr plates are presented. (W.L.H.)

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In 1954 the Oak Ridge Nationai Laboratory operated, for demonstration purposes, a high-temperature circulatingfuel reactor, employing as fuel enriched uranium fluoride dissolved in molten fluorides of other cations. A BeO moderator was used. At a maximum power of 2.5 Mw, 100 Mw hr were obtained. A negative temperature coefficient resulting largely from fuel expansion yielded exceptional stability of the reactor, and made the reactor a slave of the power demand. Xe/ sup 135/ and some of the other fission fragments are not retained in the fuel; hence, there is no xenon poisoning and relatively little danger of spreading of gaseous fission fragments in case of an accident. The advantages of liquid-fuel reactors (elimination of radiation dnmage and thermal stresses in solid fuel elements, ease of fabrication and fuel reprocessing) are combined with low pressures at very high temperatures. (auth)

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