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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 />

6

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