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ORNL-1816 - the Molten Salt Energy Technologies Web Site

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ANP QUARTERLY PROGRESS REPORT<br />

eat transfer experimentation during <strong>the</strong><br />

quarter included studies of ARE fuel in an lnconel<br />

tube, <strong>the</strong> determination of performance character-<br />

istics of an in-pile loop heat exchanger, studies of<br />

velocity and temperature distributions for several<br />

free-convection volume-heat-source systems, and<br />

prel i mi nary determi nations of flu id flow character-<br />

istics of a proposed ART core geometry. Several<br />

approximate ma<strong>the</strong>matical temperature solutions for<br />

forced-flow volume-heat-source entrance systems<br />

were developed, and <strong>the</strong> question as to whe<strong>the</strong>r<br />

electric currents which generate heat in <strong>the</strong> circu-<br />

luids of experimental volume-heat-source<br />

affect <strong>the</strong> fluid flow characteristics was<br />

The enthalpies and heat capacities of NaF-ZrF4-<br />

UF, (53-43-4 mole %) and LiF-KF-UF, (48-48-4<br />

mole %) were determined. The viscometry equip-<br />

ment was modified for greater accuracy, and new<br />

measurements were made for NaF-ZrF,-UF,. The<br />

<strong>the</strong>rmal conductivities of NaF-ZrF,-UF, and of<br />

NaF-KF-LiF with and without UF, were measured.<br />

FUSED SALT HEAT TRANSFER<br />

H. W. Hoffman J. Lones<br />

Reactor Experimental Engineering Division<br />

Prel iminary heat transfer experiments have been<br />

performed with <strong>the</strong> ARE fuel NaF-ZrF,-UF, (53.5-<br />

40-6.5 mole %) flowing in an lnconel tube. In<br />

brief, <strong>the</strong> heat transfer system used consisted of<br />

two small tanks (approximately '/,-ft3 capacity)<br />

connected by an electrically heated t-in.-OD tube<br />

with a length-to-diameter ratio of 43. Flow through<br />

<strong>the</strong> heated section was produced by helium gas<br />

pressure and controlled by an automatic cycling<br />

mechanism actuated by <strong>the</strong> fluid level in <strong>the</strong> tanks.<br />

The helium was purified by passage through a<br />

Operation of <strong>the</strong> system was terminated after<br />

115 hr in order to inspect <strong>the</strong> lnconel tube. The<br />

age fluid temperatures during <strong>the</strong> period of<br />

ation were 24 hr at 12OO0F, 85 hr at 13OO0F,<br />

and 6 hr at 1400OF. Heat transfer measurements,<br />

made in <strong>the</strong> heated section over <strong>the</strong> Reynolds<br />

modulus range of 5,600 to 10,000, yielded results<br />

below <strong>the</strong> generally accepted<br />

8. HEAT TRANSFER AND PHYSICAL PROPERTIES<br />

H. F. Poppendiek<br />

Reactor Experimental Engineering Division<br />

correlation for ordinary fluids. The precision of<br />

<strong>the</strong> measurements was approximately 10%. Visual<br />

examination of <strong>the</strong> test section after removal from<br />

<strong>the</strong> system showed no apparent film. Samples of<br />

<strong>the</strong> tube have been submitted for metallographic<br />

examination. It is recalled that in <strong>the</strong> case of <strong>the</strong><br />

previous experiments for molten NaF-KF-Li F<br />

flowing in lnconel tubes, 55% reductions in heat<br />

transfer were measured and corrosion deposits<br />

were found on <strong>the</strong> tube walls.<br />

About 15 individual heat transfer measurements<br />

were made between 24 and 115 hr of operation of<br />

<strong>the</strong> NaF-ZrF4-UF4-lnconel system. During this<br />

period no reductions of <strong>the</strong> heat transfer coef-<br />

ficients with time were observed. A new lnconel<br />

test section is currently being installed for ob-<br />

taining measurements in <strong>the</strong> period between 0 and<br />

24 hr.<br />

IN-PILE LOOP HEAT EXCHANGER ANALYSIS<br />

M. W. Rosenthal<br />

Reactor Experimental Engineering Division<br />

P. I. Perry A. D. Rossin<br />

F. D. Miraldi<br />

M.I.T. Practice School<br />

The heat exchanger for <strong>the</strong> LITR fluoride fuel<br />

loop was constructed in an unusual geometry to<br />

fit in <strong>the</strong> limited space available in a beam hole.<br />

In order to determine <strong>the</strong> operating characteristics<br />

of this exchanger, an experimental investigation<br />

of its fluid flow and heat transfer performance was<br />

conducted. The heat exchanger for <strong>the</strong> loop is<br />

formed with helical fins brazed around a section<br />

of straight pipe. The fins are enclosed in a<br />

closely fitting tube and form an annulus in which<br />

air flows in a helical path. <strong>Molten</strong> salt passes<br />

through <strong>the</strong> center tube.<br />

A duplicate of <strong>the</strong> actual exchanger to be used<br />

in <strong>the</strong> loop was connected to an air supply so that<br />

air passed through <strong>the</strong> annulus just as it would<br />

in in-pile operation. However, instead of a fused<br />

salt, dry steam was admitted to <strong>the</strong> center tube<br />

as <strong>the</strong> hot fluid. The air flow rate and inlet and<br />

outlet temperatures were measured, as were <strong>the</strong><br />

steam pressure and <strong>the</strong> condensate rate. From this<br />

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