ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
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Design work is under way on an in-pile test<br />
loop for operation in a horizontal beam hole of<br />
<strong>the</strong> MTR. This work is being done in cooperation<br />
with <strong>the</strong> Solid State Division and Pratt & Whitney<br />
Aircraft. The specifications for <strong>the</strong> loop have<br />
been established. Tests are under way on a<br />
horizontal-shaft sump pump for <strong>the</strong> loop, and a<br />
salt-to-air heat exchanger has been fabricated.<br />
The use of ARE-type sump pumps for high-flow<br />
heat exchanger tests is being investigated. The<br />
K-25 loop test of ARE components is being con-<br />
tinued as a life test of <strong>the</strong> ARE type pump, and<br />
over 3000 hr of operation has<br />
velopmental work is under way on pumps for <strong>the</strong><br />
ART, with particular emphasis being given to<br />
i mpel ler fabrication and performance.<br />
Three lnconel forced-circulation loops have been<br />
operated with NaF-ZrF,-UF,. The first two loops<br />
failed after 48 and 3 hr, respectively, but <strong>the</strong> third<br />
loop has operated for 150 hr with a Reynolds<br />
number of 10,000 and a 20OOF temperature gradient.<br />
A third bery I I i um-sodi urn-I nconel mass transfer<br />
test has been completed and has been submitted<br />
for metallographic examination, and components<br />
have been fabricated for tests of sodium in multi-<br />
metal loops.<br />
Developmental work is under way on components,<br />
such as a pump and a gas-furnace heat source,<br />
for a loop for testing fused salt-to-MaK heat ex-<br />
chanaers. A leak test has indicated that small<br />
3. EXPERIMENTAL REACTOR ENGINEERING<br />
H. W. Savage<br />
Aircraft Reactor Engineering Division<br />
PERIOD ENDING DECEMBER 10,1954<br />
o bt a i ned ich to base extrapolations of <strong>the</strong><br />
more readily obtainable out-of-pile test data. Of<br />
course, space limitations of <strong>the</strong> reactor beam<br />
holes somewhat limit <strong>the</strong> conditions obtainable<br />
in a safe and reliable experiment.<br />
The proposed test unit will consist of an 8-ft<br />
loop of %-in. schedule-40 seamless pipe with a<br />
little over 1 ft in <strong>the</strong> active zone of <strong>the</strong> reactor.<br />
The ratio of <strong>the</strong> total volume to <strong>the</strong> volume in <strong>the</strong><br />
high flux zone, known as <strong>the</strong> dilution factor, is<br />
approximately 10. Flows in <strong>the</strong> turbuleni region,<br />
Reynolds number approximately 4000, with a<br />
maximum temperature of 1500°F have been pro-<br />
posed. A temperature differential of 300°F and<br />
heat transfer of 30 to 50 kw are expected with a<br />
power density of approximately 2 kw/cm3. These<br />
conditions probably can be achieved with a fuel<br />
composed of NaF-ZrF,-UF, (53.5-40.0-6.5 mole %).<br />
Design work is proceeding on this loop and its<br />
components to meet <strong>the</strong> above specifications.<br />
Handling equipment is planned which will fa-<br />
cilitate iso<strong>the</strong>rmal operation of <strong>the</strong> loop prior to<br />
insertion into <strong>the</strong> reactor and which will also<br />
receive <strong>the</strong> radioactive materials after in-pile<br />
operation.<br />
HotizontalJhaft Sump Pump<br />
J. A. Conlin D. F. Salmon<br />
Aircraft Reactor Engineering Div i s icm<br />
Two, identical, horizontal-shaft, centrifugal-type<br />
41<br />
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