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ANP QUARTERLY PROGRESS REPORT Three of the capsules were exposed to 1.1 x 1017 t,,,. Gray-green solid residues which filled as much as 90% of the volume were found in all the capsules. The residues in the capsules exposed o a flux of 1.1 x 1017 analyzed 92% uranium, and he residues in those exposed to a flux of 2.0 x 10'' analyzed 24% uranium. In the capsules given e higher exposure, gas pressures of between 55 and 100 psi developed. Analyses of these gases showed about 30% CF, and about 25% C,F,; the remaining gas was unidentified, MINIATURE IN-PILE LOOP Bench Test W. R. Willis M. F. Osborne H. E. Robertson G. W. Keilholtz Solid State Division irst successful bench test of the miniature in-pile loop designed for insertion in a vertical hole in the LITR included four freezing and melting cycles in 260 hr of operation. The loop was oper- ated at 1466OF. The linear velocity of the fused salt circulated in the loop was between 3.3 fps (as calculated from the flowmeter) and 3.8 fps (as calculated from the pump speed); thus a Reynolds number of about 3000 was obtained. Since it was possible to freeze and melt the fused salt without causing failure of the loop, it may be advisable to fill the in-pile loop before it is inserted in the reactor and then melt the fuel mixture after the loop is in position. Since, during the bench test, the flowmeter was found to be temperature sensitive, the dependence of the measurement on the temperature must be established. The bench test was terminated because of a leak in a collar that was welded over a joint in the fuel tube. The two ends of the loop did not butt together at this location, and the annular space thus formed between the collar and the tube sections trapped the fused salt in such a manner that expansion of the salt caused the collar (not the weld) to rupture. The metal collar stretched from 0.4 in. in diameter to 0.5 in, before it ruptured, The salt from the leak, which existed during operation for about 4 hr, showed a tendency to oxidize and to stick to the lnconel surface rather than to flow rapidly down the outside tube wall. Thus, a leak in the colder portion of a loop that was operating in-pile would probably not flow downward into the high-flux region before a safety alarm from the released radioactivity could scram the reactor. A Delco motor from the group being used in bench tests has been rebuilt to withstand radiation and a higher temperature. The wire on both the rotor and the stator was replaced with glass-insulated wire, 411 paper was removed, and mica was used in the commutator and in the rotor segments; glass cloth yas used, where possible, for other insula- tion. These changes required that the shaft as- sembly be slightly modified to allow more space for windings. The rebuilt motor was tested during the bench test of the miniature loop, and it was found to be satisfactory, In a comparison of the operation of the rebuilt motor with that of the original motor under no load and under load conditions, the rebuilt motor was found to be slightly more efficient than the original motor. Furthermore, since the rebuilt motor can withstand a higher ambient temperature and since for a given voltage it produces a higher speed, higher fuel velocities can be obtained than were possible previously. Heat Transfer Calculations M. T. Robinson Solid State Division E. R. Mann F. P. Green R. S. Stone Instrumentation and Controls Division D. F. Weekes, Consultant An extensive series of heat transfer calculations has been carried out on the ORNL Reactor Controls Computer in order to predict the thermal behavior of a miniature in-pile circulating-fuel loop. The derivations of appropriate differential equations and the details of their solution are given in a forthcoming report,2 The model finally adopted for the calculations and for the in-pile loop is shown in Fig. 9.2. It was assumed to be mounted in position C-48 of the LITR, with the lower end at the location of maximum thermal-neutron flux.3 The maximum power density in the fuel in position C-48 was assumed to be 540 w/cm3. The computer results were obtained for a variety of different flow rates of fuel (NaF-ZrF,-UF,, 53.5-40-6.5 mole %) and of cooling air expressed as Reynolds number of the cooling air stream, Re, or fuel stream, Re The heat transfer, y, that is, f' *M. T. Robinson and D. F. Weekes, Design Calculation for Miniature Hi h Temperature In-Pile Circulating Fuel Loop, ORNL-1888 (' in press). 3M. T. Robinson, Solid State Semiann. Prog. Rep. Feb. 28, 1954, ORNL-1677, p 27.
the amount of heat flowing radially through a unit length of the loop, vs the distance, s, from the inlet is shown in Fig. 9.3; and the deviation, FUEL OUTLET FUEL INLET UNCLASSIFIED SSD-6-968 ORNL-LR-DWG 2252A PERIOD ENDING DECEMBER 10, 7954 of the mixed-mean fuel temperature from its average value vs s is shown in Fig, 9.4. These results meet only one of the three required boundary conditions, namely, that all fission heat be iremoved into the cooling air stream. The other conditions, that the maximum fuel temperature be 8ltiOC and that the initial air temperature be 30°C, are met by suitable interpolation of the calculated data. Some of the results of the calculations are summa- rized in Table 9.1. - 60 55 50 5 45 \ 3 - 2 40 m z a 35 5 30 \ 25 20 m>9 ORNL-LR-DMIG 3782A 15 0 20 40 60 80 102.5 125 145 165 185 205 s, DISTANCE FROM INLET (cm) I e mperat ure Air f'low 10,000 15,500 25 550 20 (scfm) 123
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ORNL DOCUMENT REFERENCE LIBRARY, Y-
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4 . CRITICAL EXPERIMENTS ..........
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Removal of Xe13' from Molten Fluori
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ANP QUARTERLY PROGRESS REPORT main
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incident on crew shield sides and r
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1. CIRCULATING-FUEL AIRCRAFT REACTO
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clean reactor at a low power for a
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for more than 0.6 Mw in the sodium,
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i PERIOD ENDING DECEMBER 70,7954 Fi
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Analytical studies, layout work, an
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XENON- REMOVAL SYSTEM 4 BLEED CIRCU
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L . PERIOD ENDING DECEMBER 70, 7954
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PERIOD ENDING DECEMBER 70, 7954
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the floor up to 3 ft below the bolt
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The pump has unusual ability to rem
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into operation with a Reynolds numb
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. . . . .- . Fig. 3.5. Heat Exchang
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TABLE 3.1. GAS-FIRED FURNACE OPERAT
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Fig. 4.1. Second Reflector-Moderate
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