ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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AMP QUARTERLY PROGRESS REPORT<br />
After the system had been thoroughly dried, all<br />
heat wes turned off and the final system completion<br />
work was begun. The mojsr work in this category<br />
consists in removing the sodium system reactor<br />
bypss, removing the flanged filter pots in the<br />
sodium purification system, and completing the<br />
enrichment system tie-in 9.0 the fuel circuit. Ther-<br />
mocouple installation also has to he completed,<br />
as we!/ as thermal insulation of the fuel pump<br />
bowls.<br />
The decision to remove the flanged filter pots<br />
and to substitute weld-senled filter pots was made<br />
several months ago, It was decided at that time,<br />
however, to postpone this substitution unti I after<br />
the water test. The original filters were useful in<br />
cleaning up the water used to test the operation of<br />
the sodium circuit. Completion of the duel enrich-<br />
ment system in no way CIffeCtad the tea test, and<br />
hence this work was postponed in the interest of<br />
completing the water test as expeditiously as<br />
possible. The fuel injection system is to be<br />
water-tested i ndependentiy of the fuel system.<br />
Insulation of the fuel pump bowls was postponed<br />
to allow more rooin for access to the pumps during<br />
the water tests. Since the pump3 hove now been<br />
checked out, the insulation iob will be completed.<br />
The system should be ready for charging with<br />
sodium early in September, and the high-trmpera-<br />
ture check out phase of the experiment will be<br />
initiated. While the sodium checks are being rui-i,<br />
the hot-gas le& test of the fuel system will be<br />
performed. This test involves loading the fuel<br />
system with mixture of helium and krypton at a<br />
pressure of about 1.5 psi. While this gas is being<br />
circulated at 1300OF' by the fuel purnp the annulus<br />
circuits will be monitored by rnoss spectrographic<br />
methods for the presence of krypton in .the annulus.<br />
'The nevtran source WQS put in the reactor, and<br />
the nuclear instrumentation was checked out. All<br />
three (the PWO regular plus the spare) fission<br />
chambers we?:^: checked, and the count-rate vs<br />
chamber-voltage curves were plotted, The data<br />
obtained provided the necessary information for<br />
establishing the operational plateau for each<br />
chambzr. Also, mechanical chaclts were mode of<br />
the perdorinnnce of the sofety and control rods.<br />
A modification of the rod-cooling circuit was<br />
required in order to minimize the heat loss from the<br />
center of the reactoi. This rieccssitated instal-<br />
lation of proportioning orifices to gat correct<br />
helium flow c.uruund th> fission chambers and the<br />
safety rods.<br />
10<br />
Final modifications of the sodium and the fuel<br />
loading systems were completed, and the building<br />
electric and helium systems were made ready to<br />
accommodate the loading facilities when they are<br />
brought into the bui Iding. Final arrangements<br />
have been completed for attaching the fuel-sampling<br />
system. This sampling system will not be left<br />
connected when the power run is initiated.<br />
The engineering prints for the entire ARE instal-<br />
lation are now up to date, and the electrical prints,<br />
in particular, were used successfully in checking<br />
out the many heater circuits involved in the experi-<br />
ment.<br />
CHARACTERISTICS ai= T HE FUEL AND THE<br />
SODIUM SYSTEMS DURING WATER TESTS<br />
The characteristics of both the fuel and the<br />
sodium systems while circulating water have been<br />
determined, Upon removal of the fuel heat ex-<br />
changer bypass loop, a glass rotameter was tempo-<br />
rarily installed in the fuel circuit between the<br />
reactor outlet and the heat exchangers. A direct<br />
calibration of the high-temperature fuel rotameter<br />
against the glass rotameter was obtained with<br />
water as the fluid. Conversion of water flow to<br />
fuel flow' is made by<br />
42<br />
where<br />
q1 = water flow (gprn) ,<br />
q2 = fuel flow (gpm) ,<br />
= water density (g/cm3) ,<br />
pf 1<br />
= fuel density (g/cm3) ,<br />
Pf2<br />
pF = flocrt density (g/cm3) .<br />
During the period of water operation, data on<br />
pump speed vs flow rate were obtained (Fig. 1.1).<br />
Also, the pressure head from the pump suction to<br />
the ieactor inlet was measured (Fig. 1.2). The<br />
system characteristics, as shown in these two<br />
ciJrves, shoirld be the same during operation with<br />
f I uor i des.<br />
'A. L. Southern. Discussion of the Rotnmeter Used in<br />
the ARE Fuel Czrcvit, ARE Files.