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ORNL-1816 - the Molten Salt Energy Technologies Web Site

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ANP QUARTERLY PROGRESS REPORT<br />

main sources: <strong>the</strong> activity of <strong>the</strong> cobalt in <strong>the</strong><br />

lnconel and <strong>the</strong> activity of <strong>the</strong> fission fragments<br />

that strike <strong>the</strong> lnconel and remain <strong>the</strong>re. The<br />

analysis showed that little would be gained by<br />

trying to obtain cobalt-free Inconel, since <strong>the</strong><br />

activity could not be reduced below that caused<br />

by <strong>the</strong> fission fragments. Adjustments are being<br />

made in <strong>the</strong> constants used in multigroup calcu-<br />

lations in order to decrease <strong>the</strong> disparity between<br />

<strong>the</strong> calculations and <strong>the</strong> results of critical experi-<br />

ments.<br />

The various types of facilities suitable for <strong>the</strong><br />

operation of <strong>the</strong> ART have been considered, and it<br />

is now planned to install <strong>the</strong> reactor assembly in a<br />

double-walled container with a water-filled annulus.<br />

The type of container was selected after careful con-<br />

sideration of <strong>the</strong> hazards involved in <strong>the</strong> operation<br />

of <strong>the</strong> reactor. This typeof installation provides for<br />

containing <strong>the</strong> products resulting from a nuclear<br />

accident and/or chemical reaction of all combusti-<br />

bles in <strong>the</strong> installation, minimizing <strong>the</strong> likelihood<br />

of serious damage from an explosion caused by<br />

sabotage or bombing, and removing and disposing<br />

of volatile fission products evolved during <strong>the</strong><br />

course of operation.<br />

3. Experimental Reactor Engineering<br />

Progress has been made in <strong>the</strong> design and testing<br />

of components for a horizontal, entirely enclosed<br />

loop for insertion in an MTR beam hole. The loop<br />

will be used to circulate proposed reactor fuels in<br />

<strong>the</strong> MTR flux so that radiation effects on <strong>the</strong> fuel<br />

can be studied. A layout arrangement of <strong>the</strong> loop<br />

has been made and is being improved consistent<br />

with specification and component changes. Tests<br />

of two horizontal-shaft sump-type pumps were made<br />

with <strong>the</strong> fluoride mixture NaF-ZrF, circulating at<br />

a temperature of 135OoF for 500 and 1000 hr,<br />

respectively. The Graphitar-lapped steel face<br />

plates wore considerably in both tests, but <strong>the</strong>y<br />

did not fail. A single-tube salt-tooair heat ex-<br />

changer that will fit inside <strong>the</strong> beam hole has been<br />

fabricated.<br />

Sump pumps of <strong>the</strong> type used in <strong>the</strong> ARE are<br />

being evaluated for application in large-scale heat<br />

exchanger tests, and pumps for ART use are being<br />

developed. One ARE-type sump pump is being<br />

tested at K-25 for performance and life determina-<br />

tions. The pump is operating at pump speeds of<br />

up to 1500 rpm at a maximum capacity of 40 gpm,<br />

and it is circulating <strong>the</strong> fluoride mixture NaF-ZrF,-<br />

UF, at a maximum pump inlet temperature of<br />

135OOF. Operating time now exceeds 3000 hr.<br />

The pumps for <strong>the</strong> ART inherently possess many<br />

imposing design problems because of <strong>the</strong>- large<br />

capacity requirements: fuel pumps, 650igpm,<br />

50-ft head; sodium pumps, 430 gpm, 125-ft head;<br />

NaK pumps, 2800 gpm, 280-ft head. Investigations<br />

of impeller cavitation characteristics and inlet<br />

and entry conditions are being made, along with<br />

studies of sealing, cooling, lubricating, and driving<br />

problems.<br />

Forced-circulation corrosion and mass transfer<br />

tests with fused salts in lnconel systems are under<br />

way. Considerable difficulty has been experienced<br />

with failures of <strong>the</strong> thin-walled tubing (\-in, OD,<br />

0.020-in. wall thickness) at bends and welded<br />

joints. The loop design has been altered by elimi-<br />

nation of <strong>the</strong> economizer and by using 0.045-in.-<br />

wall tubing. One loop of <strong>the</strong> modified design is<br />

now being operated and has accumulated about 150<br />

hr at a Reynolds number of 10,000 and a tempera-<br />

ture gradient of 200°F.<br />

A third bery I I i urn-sodi urn- lncone I mass transfer<br />

test has been completed following 1000 hr of<br />

operation. The maximum operating temperature (at<br />

<strong>the</strong> beryllium section) was 1300°F, and <strong>the</strong><br />

Reynolds number was about 190,000. Ano<strong>the</strong>r<br />

similar loop has been fabricated and is being<br />

assembled. A loop in which sodium will be circu-<br />

lated in type 316 stainless steel is being fabri-<br />

cated.<br />

The heat exchanger test program has included a<br />

header leak test and a series of pump tests with<br />

an ARE moderator-coolant type of pump. The<br />

header leak test (fuel to NaK) showed that self-<br />

plugging of an NaF-ZrF,-UF, fuel through 0.002-<br />

in.-dia leaks can occur. The pump tests showed<br />

that speeds of up to 3700 rpm could be safely<br />

achieved with this type of pump.<br />

Developmental work on a gas-furnace heat source<br />

that can be used in large heat exchanger tests was<br />

continued. A sodium-cooled 100-kw furnace was<br />

tested for about 120 hr before a gross leak termi-<br />

nated fur<strong>the</strong>r operation. An output of 85 kw was<br />

obtained at a sodium outlet design temperature of<br />

1500OF. Two natural-gas burners, based on Q<br />

design development of <strong>the</strong> Esso Marketers, were<br />

built and tested. Heat releases of 400 kw at<br />

310OOF were achieved with <strong>the</strong> first burner, and<br />

1 Mw at 330OOF was obtained with a second<br />

burner that was improved on <strong>the</strong> basis of <strong>the</strong> data<br />

obtained from <strong>the</strong> first burner.

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