ORNL-1816 - the Molten Salt Energy Technologies Web Site

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ANP QUARTERLY PROGRESS REPORT and operation is being prepared. Modifications of this vapor trap design could be used on other fused salt systems in which reliable gas con- nection is important. ADlNG OF THE ARE N. V. Smith installations for the loading of the ARE were completed during the month of October. Transfer of the barren carrier (NaF-ZrF,, 50-50 mole %) into the ARE fill tank ompleted in approximately 43 hr t. Approximately 2750 Ib of carrier ded into the fill tank, and sufficient n hand to fill the fuel system to its operating liquid level. The enriched fuel storage tank had previously been loaded with 60 Ib of carrier material for practice injections into the reactor. Tests indicated that the semiautomatic enrichment system was inadequately heated, and therefore equipment for addition of portions of the fuel concentrate (Na,UF,) directly to the circulating fuel pump was designed and assembled. In order to provide adequate means for ap- proaching criticality safely, some of the original 30-lb batches of concentrate were reduced to 10-lb batches, and, similarly, to provide accurate measurements for calibration of the control rods after criticality, 12 small batches of approximately 0.5-lb size were prepared from a 30-lb batch. The injection system consisted of a main concentrate can (containing 30, 10, or 0.5 Ib as ed) connected to an intermediate transfer can by a resistance-heated \-in. lnconel tube. The intermediate transfer can was designed so that it could be filled to a predetermined level (approximately 5.5 Ib) when the 10- or 30-lb batches were in position to be transferred. The 0.5-lb batches were transferred through a smaller intermediate can, which contained the entire small time of transfer. The intermediate can rn, connected to the fuel pump. The main transfer line to the pump was heated by calrod units, while the nozzle within the pump 18 was heated by resistance heating. The close tolerances of the injection nozzle resulted in an inherent tendency to short out and cause the nozzle tip to be cold. This, coupled with the drainage of high-melting-point material from the long transfer line, always presented the possi- bility of a frozen-fluoride plug. The first 30 Ib of concentrate was injected into the fuel pump without apl;arent difficulty. After this injection, however, difficulties in the form of line plugs and venting troubles frequently occurred. After 48 hr, most of these problems were under control, and loading of the enriched concentrate proceeded smoothly. The reactor was brought to criticality, and small injections of 0.5-lb batches were made for the control rod calibrations. At the completion of the final small addition, the transfer line broke and simultane- ously plugged at the injection nozzle. Efforts to repair the damage were fruitless, and the final injection of 30 Ib of the concentrate to allow ARE operation at power was made through the sample line into the pump. ANALYSIS OF LEAK IN SODIUM SYSTEM E. E. Hoffman W. H. Cook C. F. Leitten Metal lurgy Division The sodium system of the ARE was filled initially on September 26, 1954, but the sodium had to be dumped on September 27 because of a leak at a tube bend in the sodium purification system. The section of austenitic stainless steel pipe in which the leak occurred was located just ahead of the filter traps. The system had been filled with sodium for 37 hr and had reached a maximum temperature of approximately 1150°F before the leak was detected. A portion of the section removed and the location of the leak are shown in Fig. 1.6. The leak occurred where a metal thermocouple protection tube had been attached to the stainless steel pipe by Heliarc welding. The attack around the weld was due to the formation of sodium oxide as the sodium leaked through the weld. The inside of the pipe at the weld may be seen in Fig. 1.7. An excessive amount of penetration was obtained during the welding operation. The large weld nugget cracked during cooling after welding. A cross section of the weld crack is shown in Fig. 1.8. Examination of the pipe in this section revealed a " . . -
i PERIOD ENDING DECEMBER 70,7954 Fig. 1.6. Section of Tube Bend Showing Location of Sodium Leak in Type 347 Stainless Steel Pipe Where Thermocouple Well Had Been Attached. Inset shows location of leak at higher magnification. s from 76 to 135 mils, and the spectrographic examination revealed that two pieces of pipe in this section were type 347 stainless steel, while the other two were type 316 stainless steel. Chemical analyses of three sodium samples taken n from this section indicated e s . .. cause of the excessive penetration enetration can probably ge on the walll thicknesses in this section. W. R. Grimes D. R. Cuneo e ARE fuel for analysis during operation of the reactor 19
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