ORNL-1816 - the Molten Salt Energy Technologies Web Site

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t INSTRUMENT CONFERENCE -NEW 26-ft-HIGH X 30-ft-WIDE ROLL- UP DOOR. -, LEGEND POURED CONCRETE SOLID CONCRETE BLOCKS @ CORED CONCRETE BLOCKS * 1 ‘ . I ’ # CONTROL ROOM - PART FIRST FLOOR PLAN EXISTING BUILDING 2 0 4 8 12 16 20 FEET 48-in. BLOWERS ”’ yp 64 ft 0 in. ADDITION -1 k5 FIELD MAINTENANCE SHOP PART BASEMENT PLAN Fig. 2.8. Layout Plan of Proposed ART Installation in Addition to Present ARE Building. UNCLASSIFIED ORNL-LR-DWG 4471 5J -i 2 !7 2 0 XJ z:
the floor up to 3 ft below the bolting flange level. The reactor tank location would be approximately centered in the 42-ft-wide, 64-ft-long high-bay ex- tension directly in line with the ARE experimental bay. The reactor would be positioned so that the top of the shield would be at the building floor elevation. To permit use of the experimental pits for installation of auxiliary equipment, to permit possible underwater reactor disassembly work after reactor operation, and to provide a large entry door to the ART area, the south wall of the ARE experimental bay would be removed, the overhead crane facility would be revised from 10- to 20-ton capacity, and the truck door in the north wall of the ARE Building would be enlarged. The double-walled tank described above is essentially the container considered for this installation. The inner tank, or pressure vessel, would be approximately 24 ft in diameter with a straight section about 11 ft long and a hemispherical bottom and top. The joint between the removable top and the lower portion of the tank would probably be a bolting flange, with provision for sealing the joint with a low-melting-point alloy. Thus the top would be used only as required by the operating program. The outer tank would be a right circular cylinder approximately 27 ft in diameter and about 47'/, ft high. About 26 ft of this water-containing tank would be above floor grade, and this portion of the tank would be attached by a flange or weld joint only when the operating program required that the upper hemisphere of the inner tank be in place. The inner tank would be set coaxially with the PERIOD ENDING DECEMBER 10,1954 movement of the portable fluoride fuel and sodium moderator coolant containers to their operating stations under the reactor. The off-center location would also serve to minimize the length of NaK piping that must run from the reactor through a bulkhead in the pressure vessel to the he'gt dump radiators outside the tank. Quite a variety of shields has been corisidered for the ART. The most convenient seems to be one functionally the same as that for an aircraft requiring a unit shield, namely, a shield designed to give 1 r/hr at 50 ft from the center of the reactor. Such a shield is both the lightest and mast com- pact that has been devised. It makes use of non- critical materials that are in good supply, and it will provide useful performance data on the effects of the release of delayed neutrons ancl decay gammas in the heat exchanger, the generation of secondary gammas throughout the shield, etc. While the complication of detailed instrumentation within the shield does not appear to be warranted, it will be extremely worthwhile to obtain radiation dose level data at various points around the pe- riphery of the shield, particularly in the vicinity of the ducts and the pump and expansion tank region. Several arrangements have been considered as a means for disposing of the heat generated in the reactor. The most promising is one that resembles a turbojet power plant in many respects. It em- ploys radiators essentially similar to tho:je suit- able for turbojet operation. Conventional axial-flow blowers would be employed to force cooling air through the radiators. This arrangement is flexible This positioning would provide needed space for radiators would be mounted in an air tunnel which 39
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