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ORNL-1771 - Oak Ridge National Laboratory

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ANP QUARTERLY PROGRESS REPORT<br />

approximately 1 /,6 in. It is concluded that no<br />

problem will be encountered in the use of similarly<br />

equipped motors in the ARE.<br />

REACTOR SYSTEM COMPONENT TEST LOOP<br />

Operation of Leap<br />

W. 6. Cobb A. G. Grindell<br />

Aircraft Reactor Engineering Division<br />

D. 5. Trauger G. A. Kuipers<br />

Technical Division, K-25<br />

Operation of the reactor system component test<br />

loop' Qt K-25 was temporarily halted after 1047 hr<br />

of operation to remove one ARE core hairpin tube<br />

for metallographic examination. Shutdown, tube<br />

removal, tube replacement, and re-startup were<br />

accomplished under a complete helium blanket to<br />

prevent air from contaminating the fluoride mixture<br />

or the inside of the lnconel system. An irradiated<br />

V-belt that was installed, as described above,<br />

after 875 hr of system operation ha5 operated for<br />

more than 900 hr of the approximately 1800 hr<br />

of system operation. Plugging of gas line con-<br />

nections to the pump tank by ZrF4-vapor condensate<br />

has occurred periodically. In some instances the<br />

plugs have been removed by heating the gas line<br />

involved and blowing the vaporized ZrF, back<br />

into the pump tank. No completely satisfactory<br />

solution to this problem has been found to date;<br />

the use of a large-capacity vapor trap is being<br />

studied as a possible solution.<br />

8H. W. Savage ef al., ANP Qua. Prog. Rep. June 10,<br />

1954, <strong>ORNL</strong>-1729, p 14.<br />

16<br />

Examination of Hairpin Tube<br />

G. M. Adamson R. S. Crouse<br />

Meta I I urgy Division<br />

Metallographic examination of the hairpin tube<br />

showed normal subsurface void attack. The maxi-<br />

ilium penetration was to a depth of 5 mils. There-<br />

fore it appears that corrosion from impurities will<br />

not be a serious problem in the ARE. Since this<br />

loop was not precleaned, the corrosive conditions<br />

should have been worse than those in the ARE.<br />

No information on the amount of corrosion that<br />

may be expected from mass transfer could be<br />

obtained because the loop is being operated iso-<br />

thermally.<br />

REACTOR PHYSICS<br />

M. E. LaVerne<br />

C. B. Mills<br />

W. K. Ergen<br />

R. R. Coveyou<br />

Aircraft Reactor Engineering Division<br />

R. Bate C. S. Burtnette<br />

United States Air Force<br />

The Eyewash code, developed by the <strong>ORNL</strong><br />

Mathematics Panel for use on the UNIVAC, yielded<br />

the following results for the ARE: critical mass,<br />

30 Ib of U235; UZ3' required to yield the 4% excess<br />

reactivity needed for operation, 35 Ib; keff for<br />

40 Ib of U235, 1.07; critical mass without controls,<br />

safety, or instrument apparatus, 17 Ib (this emphasizes<br />

the high cost of these materials); hk/(h~/~)=<br />

0.232; temperature coefficient applicable to slow<br />

temperature changes and due to expansion of the<br />

whole reactor and to thermal base effects,<br />

-4.3 x 10-5/0F; reactivity value of U235 in tube<br />

bends at reactor ends, 0.006'in keff.

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