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32 BELL et al.<br />

"5?<br />

A<br />

O<br />

3 _ - O<br />

D<br />

C 2 -<br />

1 --<br />

1<br />

1.0-<br />

1.2-<br />

1.4-<br />

1.6-<br />

I I<br />

1.1 MA<br />

1.3<br />

1.5<br />

1.7<br />

AAj<br />

I I<br />

D<br />

D ft<br />

i<br />

.§!<br />

c6<br />

S DD -<br />

" V i<br />

i<br />

0 10 20 30<br />

NEUTRAL INJECTION POWER (MW)<br />

FIG. 2. Scaling of the peak neutron flux from D-D fusion reactions with neutral beam injection power.<br />

Some discharges with current ramping during the NBI pulse are included.<br />

o<br />

Z. 2<br />

1 -<br />

A<br />

O<br />

_ o D<br />

1.0-<br />

1.2-<br />

1.4-<br />

1.6-<br />

i i<br />

1.1 MA<br />

1.3<br />

1.5<br />

1.7<br />

I I<br />

10<br />

(mag),2<br />

(E (MJ<br />

tot '<br />

2 )<br />

I<br />

I<br />

15 20<br />

F/G. 5. Scaling of the peak neutron flux with the square of the peak stored energy for the intersection<br />

of the data sets in Figs. 1 <strong>and</strong> 2.<br />

achievement of good confinement is a reduction in hydrogen isotope recycling<br />

at the limiter. In the degassing procedure described in Refs. [2], [7],<br />

<strong>and</strong> [9], low-density helium discharges at modest plasma current are used<br />

to remove deuterium from the surface layers of the graphite limiter. This<br />

degassing is evidenced by a drop in D/3 emission <strong>and</strong> a reduction in the de-

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