ORNL-1816 - the Molten Salt Energy Technologies Web Site

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 instal-
lation 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 instal-
lation. 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
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