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ORNL-1771 - Oak Ridge National Laboratory

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ANP QUARTERLY PROGRESS REPORT<br />

TABLE 2.2. REFLECTOR-MODERATED REACTOR POWER PLANT SYSTEM DATA<br />

.II__.__..._._.. .<br />

NaK in rodiator cares, Ib<br />

Header drums<br />

Radiator tubes<br />

Outlet lines<br />

Inlet lines<br />

Intermediate heat exchanger<br />

NaK flowing in circuits, Ib<br />

NaK in header tanks, Ib<br />

Total NaK in complete power plant, Ib<br />

NaK flow rate through rodiotor circuits (for a 4OO0F AT), cfs<br />

NaK transit time through system, sec<br />

NaK transit time through intermediate heat exchanger, sac<br />

NaK transit time through radiator tubes, sec<br />

Fuel in core circuit (flowing), ft3<br />

Fuel in header tank, ft3<br />

Fuel in core, ft<br />

3<br />

Fuel flow rate, sfs<br />

Fuel circuit transit time, sec<br />

Thermal capacities of power plant, Btu/OF<br />

Radiator cores<br />

Lines and pumps<br />

NaK (flowing)<br />

Intermediate heat exchanger<br />

Total for NaK systems<br />

Fuel<br />

Total for power plant, Btu/OF<br />

nuclear power. Even if a leak should develop in<br />

one of the welds, there would be no serious contamination<br />

problem. Upon completion of the endurance<br />

test, it should not be difficult to make a<br />

thorough inspection of the parts - something that<br />

could hardly be done after sustained operation at<br />

high nuclear power.<br />

At first thought, the ZPU might appear to delay<br />

the program, but closer inspection indicates that<br />

it may actually save a substantial amount of time,<br />

because efforts to get it into operation can proceed<br />

at full speed without the inevitable hazards, re-<br />

20<br />

200-Mw<br />

Full-Scale 60-MW CFRE<br />

Aircraft<br />

128<br />

128<br />

800<br />

900<br />

450<br />

2300<br />

500<br />

2800<br />

40<br />

1.25<br />

0.23<br />

0.067<br />

6<br />

1<br />

1.8<br />

12.0<br />

O s 5<br />

600<br />

250<br />

600<br />

250<br />

1700<br />

300<br />

2000<br />

40<br />

40<br />

240<br />

270<br />

135<br />

680<br />

150<br />

84 0<br />

12.6<br />

1.25<br />

0.23<br />

0.067<br />

3.9<br />

0.4<br />

1.8<br />

2.7<br />

0.7<br />

180<br />

75<br />

180<br />

75<br />

____<br />

51 0<br />

210<br />

720<br />

straints, inhibitions, and hesitations that would<br />

accompany high nuclear power operation. Work on<br />

the CFRE can proceed at a inore deliberate pace,<br />

and the mistakes disclosed by work on the ZPU<br />

can be avoided. The degree to which the ZPU<br />

will be a mockup of the CFRE will depend upon<br />

the problems that develop in the course of the<br />

component test work. It is hoped that a 104w<br />

gas-fired furnace can be used, in place of one of<br />

the two CFRE heat dumps, in making some heat<br />

transfer tests on the fluoride-to-NaK heat exchanger<br />

and in obtaining a temperature gradient

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