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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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.